The standards of Radiation Protection of IAEA

International Nuclear Information System (INIS)

Butragueno, J. L.

2000-01-01

Nuclear Safety and Radiation Protection are technological disciplines whose international character have been recognised since the very beginning. Safety culture and the defense in depth criterium address in the same way this international collaboration. The International Atomic Energy Agency, with headquater in Vienna, is specially sensitive to this aspect and a significant amount of resources has been dedicated to the promotion of a closer international collaboration through the promotion of two complementary programs: the Convention on Nuclear Safety and the Convention on Rad waste Management, and the reconstruction of a great piramide of standards, that staring with Fundamental Principles, is followed with a set of Basic Safety Standards and completed with Safety Requirements and additional technical information, that provide practical ways to implement the Fundamental Principles. This article describe briefly the RASS Program of the IAEA (Radiation Safety Standards) and the work of the Technical Committees established to assess the Director General of the IAEA in this task. (Author)

Quality standards: Comparison between IAEA 50-C/SG-Q and ISO 9001:2000

International Nuclear Information System (INIS)

2002-01-01

The International Atomic Energy Agency (IAEA) has the statutory mandate to seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world. As part of the activities to achieve its objectives, the IAEA is authorized to establish standards of safety for the protection of health and the minimization of danger to life and property. The standards of safety developed by the IAEA are recommendations for use by its Member States in the framework of national regulations for the safe utilization of nuclear energy. Such standards should be considered as nuclear safety regulatory documents. The standards developed by the International Organization for Standardization (ISO) are complementary technical documents emphasizing industrial application and contractual aspects. Regarding the quality assurance topic, the IAEA developed the publication Safety Series No. 50-C/SG-Q, Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Installations, which is mostly used directly or indirectly to establish the nuclear safety requirements at the nuclear utility-regulator interface. The ISO 9001:2000 standard, Quality Management Systems Requirements, is often used to define the quality management system requirements at the utility-supplier interface. The relationship between the IAEA and ISO quality standards is growing in significance owing to their increasing impact upon utilities (owners/operators of nuclear facilities) and their contractors/suppliers. The relationship between the IAEA and ISO standards is considered critical in particular with respect to contractors/suppliers with a small range of nuclear supplies. These contractors-suppliers are not always willing to prepare special quality assurance programmes based on nuclear safety standards. On the other hand, these contractors/suppliers may be qualified on the basis of the ISO quality standard. In any case, for delivering nuclear items and services the

DS424: A Roadmap for the Implementation of the IAEA Safety Standards

International Nuclear Information System (INIS)

Yllera, Javier

2010-01-01

Many countries interested in developing nuclear power programmes for the first time need to have experience in using and regulating radioactive source materials. They need to have experience in building and operating large non-nuclear construction projects. Nuclear power has unique attributes and commitments associated with it that other industries do not. Although undertaken as a national endeavour with many national implications, building and operating a nuclear facility also has global implications (financial, political, safety, etc.). DG’s 2008 General Conference speech: “Every country has the right to introduce nuclear power, as well as the responsibility to do it right.”. The development of IAEA Safety Standards is an statutory function of the IAEA (article III of the IAEA Statute): “The Agency is authorized to establish or adopt… standards of safety for protection of health and minimization of danger to life and property…”. New guide (DS 424) constitutes a “Road-map” to apply the entire suite of IAEA Safety Standards progressively during the early phases of the implementation of a nuclear power programme. IAEA safety review missions based on internationally agreed safety standards are well established and are the best tools to build up confidence on the capacity of a country to develop nuclear energy in a safe way

Recent developments in the IAEA safety standards: design and operation of nuclear power plants

International Nuclear Information System (INIS)

Saito, Takehiko

2004-01-01

The IAEA has been publishing a wide variety of safety standards for nuclear and radiation related facilities and activities since 1978. In 1996, a more rigorously structured approach for the preparation and review of its safety standards was introduced. Currently, based on the approach, revision of most of the standards is in completion or near completion. The latest versions of the Safety Requirements for ''Design'' and ''Operation'' of nuclear power plants were respectively published in 2000. Currently, along with this revision of the Safety Requirements, many Safety Guides have been revised. In order to clarify the complicated revision procedure, an example of the entire revision process for a Safety Guide is provided. Through actual example of the revision process, enormous amount of work involved in the revision work is clearly indicated. The current status of all of the Safety Standards for Design and that for Operation of nuclear power plants are summarized. Summary of other IAEA safety standards currently revised and available related IAEA publications, together with information on the IAEA Web Site from where these documents can be downloaded, is also provided. The standards are reviewed to determine whether revision (or new issue) is necessary in five years following publication. The IAEA safety standards will continue to be updated through comprehensive and structured approach, collaboration of many experts of the world, and reflecting good practices of the world. The IAEA safety standards will serve to provide high level of safety assurance. (author)

New requirements on safety of nuclear power plants according to the IAEA safety standards

International Nuclear Information System (INIS)

Misak, J.

2005-01-01

In this presentation author presents new requirements on safety of nuclear power plants according to the IAEA safety standards. It is concluded that: - New set of IAEA Safety Standards is close to completion: around 40 standards for NPPs; - Different interpretation of IAEA Safety Standards at present: best world practices instead of previous 'minimum common denominator'; - A number of safety improvements required for NPPs; - Requirements related to BDBAs and severe accidents are the most demanding due to degradation of barriers: hardware modifications and accident management; - Large variety between countries in implementation of accident management programmes: from minimum to major hardware modifications; -Distinction between existing and new NPPs is essential from the point of view of the requirements; WWER 440 reactors have potential to reflect IAEA Safety Standards for existing NPPs; relatively low reactor power offers broader possibilities

Safety first. Status reports on the IAEA's safety standards

International Nuclear Information System (INIS)

Webb, G.; Karbassioun, A.; Linsley, G.; Rawl, R.

1998-01-01

Documents in the IAEA's Safety Standards Series known as RASS (Radiation Safety Standards) are produced to develop an internally consistent set of regulatory-style publications that reflects an international consensus on the principles of radiation protection and safety and their application through regulation. In this article are briefly presented the Agency's programmes on Nuclear Safety Standards (NUSS), Radioactive Waste Safety Standards (RADWASS), and Safe Transport of Radioactive Materials

Standards in radiation protection at the IAEA Dosimetry Laboratory

International Nuclear Information System (INIS)

Czap, L.; Pernicka, F.; Matscheko, G.; Andreo, P.

1999-01-01

Approximately 90% of the Secondary Standard Dosimetry Laboratories (SSDLs) provide users with calibrations of radiation protection instruments, and the Agency is making every necessary effort to insure that SSDLs measurements in radiation protection are traceable to Primary Standards. The IAEA provides traceable calibrations of ionization chambers in terms of air kerma at radiation protection levels and ambient dose equivalent calibrations. SSDLs are encouraged to use the calibrations available from the Agency to provide traceability for their radiation protection measurements. Measurements on diagnostic X ray generators have become increasingly important in radiation protection and some SSDLs are involved in such measurements. The IAEA has proper radiation sources available to provide traceable calibrations to the SSDLs in this field, including an X ray unit specifically for mammography dedicated to standardization procedures. The different photon beam qualities and calibration procedures available in the Agency's Dosimetry Laboratory will be described. (author)

Quality assurance standards: comparison between IAEA 50-C/SG-Q and ISO 9001:1994

International Nuclear Information System (INIS)

2000-11-01

The International Atomic Energy Agency (IAEA) and the International Organization for Standardization (ISO) agreement regarding the scope and coverage of documents published by both organizations points out that the standards of safety developed by the IAEA are recommendations for use by its Member States in the framework of national regulations for the safe utilization of nuclear energy. Such standards should be considered as nuclear safety regulatory documents. The standards developed by the ISO are complementary technical documents emphasizing industrial application and contractual aspects. Regarding the quality assurance topic, the IAEA standards 50-C/SG-Q are mostly used directly or indirectly to establish the nuclear safety requirements at the utility-regulatory interface. The industrial ISO 9001 standards have progressively been used to implement the quality assurance requirements at the interface utility-supplier. The relationship between both standards is growing in significance owing to the impact upon the owners/operators of nuclear facilities and their contractors/suppliers. The relationship between the IAEA and ISO standards is considered critical, in particular regarding suppliers with a small range of nuclear supplies. These organizations are not always willing to prepare special quality assurance programmes based on nuclear safety standards. On the other hand, these organizations may be qualified on the basis of the ISO quality assurance standards. In any case, for delivering nuclear items and services the quality assurance programme must comply with the requirements established in the nuclear safety regulatory standards. This implies that the utility-supplier will have to demonstrate that the acceptable degree of quality assurance in relation to nuclear safety is accomplished. This may be achieved by imposing additional requirements on the supplier over and above those contained within the ISO. In order to provide a description of the differences

Standardization of the calibration of brachytherapy sources at the IAEA dosimetry laboratory

International Nuclear Information System (INIS)

Shanta, A.; Andreo, P.

1996-01-01

A new service to SSDLs has been initiated at the IAEA Dosimetry Laboratory for providing calibrations of well-type ionisation chambers, used in brachytherapy applications, which are traceable to the International Measurement System. Considering that the most common radionuclide used in the developing countries is 137 Cs, two such sources of the type used for gynaecological intracavitary applications have been purchased by the Agency and calibrated at the National Institute of Standards and Technology (NIST), USA. These 137 Cs reference sources together with a well-type ionization chamber constitute the IAEA brachytherapy dosimetry standard. Based on the recommendations by a group of experts, a method has been developed for transferring calibrations to SSDLs which is described in this paper. The method is based on the acquisition by the SSDLs of sources and equipment similar to those at the IAEA. The well-type chamber is to be calibrated at the IAEA Dosimetry Laboratory, and this will be used at the SSDL to calibrate its own reference sources. These sources can in turn by used to calibrate well-type chambers from hospital users and to calibrate other type of sources by performing measurements in air. In order to standardize the procedures for the two methods and to provide guidance to the SSDLs, measurements have been carried out at the IAEA Dosimetry Laboratory. The reproducibility of the two type of measurements has been found to be better than 0.5%, and the uncertainty of calibrations estimated to be less than 1.5% (one standard deviation). (author). 8 refs, 8 figs, 2 tabs

Improving the Transparency of IAEA Safeguards Reporting

International Nuclear Information System (INIS)

Toomey, Christopher; Hayman, Aaron M.; Wyse, Evan T.; Odlaug, Christopher S.

2011-01-01

In 2008, the Standing Advisory Group on Safeguards Implementation (SAGSI) indicated that the International Atomic Energy Agency's (IAEA) Safeguards Implementation Report (SIR) has not kept pace with the evolution of safeguards and provided the IAEA with a set of recommendations for improvement. The SIR is the primary mechanism for providing an overview of safeguards implementation in a given year and reporting on the annual safeguards findings and conclusions drawn by the Secretariat. As the IAEA transitions to State-level safeguards approaches, SIR reporting must adapt to reflect these evolutionary changes. This evolved report will better reflect the IAEA's transition to a more qualitative and information-driven approach, based upon State-as-a-whole considerations. This paper applies SAGSI's recommendations to the development of multiple models for an evolved SIR and finds that an SIR repurposed as a 'safeguards portal' could significantly enhance information delivery, clarity, and transparency. In addition, this paper finds that the 'portal concept' also appears to have value as a standardized information presentation and analysis platform for use by Country Officers, for continuity of knowledge purposes, and the IAEA Secretariat in the safeguards conclusion process. Accompanying this paper is a fully functional prototype of the 'portal' concept, built using commercial software and IAEA Annual Report data.

The IAEA safety standards for radiation, waste and nuclear safety

International Nuclear Information System (INIS)

Gonzalez, Abel J.

1997-01-01

This paper presents a brief description of the standards for radiation, waste and nuclear safety established by the International Atomic Energy Agency (IAEA). It provides a historical overview of their development and also summarizes the standards' current preparation and review process. The final paragraphs offer an outlook on future developments. (author)

IAEA Safety Standards on Management Systems and Safety Culture

International Nuclear Information System (INIS)

Persson, Kerstin Dahlgren

2007-01-01

The IAEA has developed a new set of Safety Standard for applying an integrated Management System for facilities and activities. The objective of the new Safety Standards is to define requirements and provide guidance for establishing, implementing, assessing and continually improving a Management System that integrates safety, health, environmental, security, quality and economic related elements to ensure that safety is properly taken into account in all the activities of an organization. With an integrated approach to management system it is also necessary to include the aspect of culture, where the organizational culture and safety culture is seen as crucial elements of the successful implementation of this management system and the attainment of all the goals and particularly the safety goals of the organization. The IAEA has developed a set of service aimed at assisting it's Member States in establishing. Implementing, assessing and continually improving an integrated management system. (author)

The IAEA Promotes the Application of Safety Standards and Best Practices for the Management of Radioactive Waste

International Nuclear Information System (INIS)

2014-01-01

The IAEA works to promote a high level of safety as it facilitates peaceful uses of nuclear energy worldwide. The IAEA’s Statute authorizes it to establish or adopt standards of safety for protection of health and minimization of danger to life and property, and to provide for the application of these standards. The Statute also mandates the IAEA to foster the exchange of scientific and technical information to facilitate the peaceful uses of atomic energy. To this end, the IAEA develops safety standards on different topics, including on the safety of radioactive waste management. These standards, issued in the IAEA Safety Standards Series, reflect an international consensus on what constitutes a high level of safety for protecting people from harmful effects of ionizing radiation and protecting the environment

Best Estimate plus Uncertainty (BEPU) Analyses in the IAEA Safety Standards

International Nuclear Information System (INIS)

Dusic, Milorad; )

2013-01-01

The Safety Standards Series establishes an essential basis for safety and represents the broadest international consensus. Safety Standards Series publications are categorized into: Safety Fundamental (Present the overall objectives, concepts and principles of protection and safety, they are the policy documents of the safety standards), Safety Requirements (Establish requirements that must be met to ensure the protection and safety of people and the environment, both now and in the future), and Safety Guides (Provide guidance, in the form of more detailed actions, conditions or procedures that can be used to comply with the Requirements). The incorporation of more detailed requirements, in accordance with national practice, may still be necessary. There should be only one set of international safety standards. Each safety standard will be reviewed by the relevant committee or by the commission every five years. Best Estimate plus Uncertainty (BEPU) Analyses are approached in the following IAEA Safety Standards: - Safety Requirements SSR 2/1 - Safety of NPPs, Design (Revision of NS-R-1); - General Safety Requirement GSR Part 4: Safety Assessment for Facilities and Activities; - Safety Guide SSG-2 Deterministic Safety Analysis for Nuclear Power Plants. NUSSC suggested that new safety guides should be accompanied by documents like TECDOCs or Safety Reports describing in detail their recommendations where appropriate. Special review is currently underway to identify needs for revision in the light of the Fukushima accident. Revision will concern, first, the Safety Requirements, and then, the Selected Safety Guides

Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants

International Nuclear Information System (INIS)

2016-05-01

Revised to take into consideration findings from the Fukushima Daiichi nuclear power plant accident, IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, has introduced some new concepts with respect to the earlier safety standard published in the year 2000. The preparation of SSR-2/1 (Rev. 1) was carried out with constant and intense involvement of IAEA Member States, but some new requirements, because of the novelty of the concepts introduced and the complexity of the issues, are not always interpreted in a unique way. The IAEA is confident that a complete clarification and a full understanding of the new requirements will be available when the supporting safety guides for design and safety assessment of nuclear power plants are prepared. The IAEA expects that the effort devoted to the preparation of this publication, which received input and comments from several Member States and experts, will also facilitate and harmonize the preparation or revision of these supporting standards

The IAEA/WHO network of Secondary Standard Dosimetry Laboratories. SSDL network charter

International Nuclear Information System (INIS)

1999-04-01

In 1976, the International Atomic Energy Agency (IAEA) together with the World Health Organization (WHO) established a Network of Secondary Standard Dosimetry Laboratories (SSDLs), known as the IAEA/WHO SSDL Network. This Network, through SSDLs designated by Member States, provides a direct linkage of national dosimetry standards to the international measurement system of standards traceable to the Bureau International des Poids et Mesures (BIPM), and the dissemination of S.I. quantities and units through the proper calibration of field instruments by the SSDLs. The Network has proved to be of value in improving national capabilities for instrument calibration and the awareness of better accuracy and traceability. Fifty-eight countries have nominated SSDLs for membership in the Network. Unfortunately, some of these SSDLs do not yet function as full members, perhaps because of some uncertainty as to their obligations concerning the Network. Consequently, the Scientific Committee which advises the Network Secretariat has recommended that a Charter be drawn up explaining the privileges, rights and duties of members in the Network which would strengthen their links to the international measurement system. In addition to the duties of members in the Network and the benefits that full members can receive, the Charter also describes how the Network functions and the scope of the work of the SSDLs. In producing this Charter, the advisory group has drawn heavily on the IAEA publication 'Secondary Standard Dosimetry Laboratories: Development and Trends' (1985) which summarizes the origin, development, status and prospects of the IAEA/WHO SSDL Network. The various appendices are effectively up-dates of different parts of this earlier publication, and the original drafting and reviewing bodies are given due recognition. The revisions take into account the experience the Agency has gained in coordinating the activities of the Network for more than 20 years

The IAEA/WHO network of Secondary Standard Dosimetry Laboratories. SSDL network charter

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-04-01

In 1976, the International Atomic Energy Agency (IAEA) together with the World Health Organization (WHO) established a Network of Secondary Standard Dosimetry Laboratories (SSDLs), known as the IAEA/WHO SSDL Network. This Network, through SSDLs designated by Member States, provides a direct linkage of national dosimetry standards to the international measurement system of standards traceable to the Bureau International des Poids et Mesures (BIPM), and the dissemination of S.I. quantities and units through the proper calibration of field instruments by the SSDLs. The Network has proved to be of value in improving national capabilities for instrument calibration and the awareness of better accuracy and traceability. Fifty-eight countries have nominated SSDLs for membership in the Network. Unfortunately, some of these SSDLs do not yet function as full members, perhaps because of some uncertainty as to their obligations concerning the Network. Consequently, the Scientific Committee which advises the Network Secretariat has recommended that a Charter be drawn up explaining the privileges, rights and duties of members in the Network which would strengthen their links to the international measurement system. In addition to the duties of members in the Network and the benefits that full members can receive, the Charter also describes how the Network functions and the scope of the work of the SSDLs. In producing this Charter, the advisory group has drawn heavily on the IAEA publication 'Secondary Standard Dosimetry Laboratories: Development and Trends' (1985) which summarizes the origin, development, status and prospects of the IAEA/WHO SSDL Network. The various appendices are effectively up-dates of different parts of this earlier publication, and the original drafting and reviewing bodies are given due recognition. The revisions take into account the experience the Agency has gained in coordinating the activities of the Network for more than 20 years.

Euratom's accounting procedures to comply with IAEA requirements

International Nuclear Information System (INIS)

Kschwendt, H.

1980-01-01

The accounting concept used by the operators for nuclear materials accountancy is different from the evaluation concept used by IAEA. Euratom integrated these two concepts thus allowing for an automatic transformation from the one to the other concept (establishment of reports to IAEA by computer). Particular procedures have been developed to ensure the corrections of the accountancy in both concepts and to perform the retrospective corrections as required by IAEA. 4 refs

The IAEA concept of detection of diversion through nuclear material accountancy (2)

International Nuclear Information System (INIS)

Akiba, Mitsunori

2005-01-01

Diversion into D (falsification of accounting report) and diversion into MUF could be detected by the Inspectorate through nuclear material accountancy. The Inspectorate designs inspection activities to detect diversion into D in cost effective ways. As a result, detection of diversion into D is divided into two statistics, one is item difference statistics which could detect major defects and the other is material balance statistics which could detect remaining small defects. MUF statistics could detect Diversion into MUF. Item statistics has many useful characteristics from safeguards view points, so it is examined in details. Material balance statistics and MUF statistics stem from measurement error associated with equipment inevitably. The above-mentioned concept is called 'IAEA decision structure'. Hereafter, designing safeguards (inspection activities) approach will be based on the IAEA decision structure. (author)

The IAEA safety standards

International Nuclear Information System (INIS)

Karbassioun, Ahmad

1995-01-01

During the development of the NUSS standards, wide consultation was carried out with all the Member States to obtain a consensus and the programme was supervised by a Senior Advisory Group consisting of senior safety experts from 13 countries. This group of senior regulators later became what is now known as the Nuclear Safety Standards Advisory Group (NUSSAG) and comprises of senior regulatory experts from 16 countries. The standards that were developed comprise of four types of documents: safety fundamentals; codes of practice; safety guides; and safety practices. The safety fundamentals set out the basic objectives, concepts and principles for nuclear safety in nuclear power plants. The codes of practice, are of a legislative nature, and establish the general objectives that must be fulfilled to ensure adequate nuclear power plant safety. They cover five areas: governmental organization; siting, design, operation and quality assurance. The safety guides, administrative in character, recommend procedures and acceptable technical solutions to implement the codes and guides by presenting further details gained from Member States, on the application and interpretation of individual concepts in the NUSS codes and guides. In total in the NUSS series there is currently one Fundamentals document, five Codes of Practice and fifty-six Safety Guides

IAEA safety standards for research reactors

International Nuclear Information System (INIS)

Abou Yehia, H.

2007-01-01

The general structure of the IAEA Safety Standards and the process for their development and revision are briefly presented and discussed together with the progress achieved in the development of Safety Standards for research reactor. These documents provide the safety requirements and the key technical recommendations to achieve enhanced safety. They are intended for use by all organizations involved in safety of research reactors and developed in a way that allows them to be incorporated into national laws and regulations. The author reviews the safety standards for research reactors and details their specificities. There are 4 published safety standards: 1) Safety assessment of research reactors and preparation of the safety analysis report (35-G1), 2) Safety in the utilization and modification of research reactors (35-G2), 3) Commissioning of research reactors (NS-G-4.1), and 4) Maintenance, periodic testing and inspection of research reactors (NS-G-4.2). There 5 draft safety standards: 1) Operational limits and conditions and operating procedures for research reactors (DS261), 2) The operating organization and the recruitment, training and qualification of personnel for research reactors (DS325), 3) Radiation protection and radioactive waste management in the design and operation of research reactors (DS340), 4) Core management and fuel handling at research reactors (DS350), and 5) Grading the application of safety requirements for research reactors (DS351). There are 2 planned safety standards, one concerning the ageing management for research reactor and the second deals with the control and instrumentation of research reactors

The IAEA/WHO Network of SSDLs. Short history, activity and future trends[Secondary Standard Dosimetry Laboratories

Energy Technology Data Exchange (ETDEWEB)

Svensson, Hans; Zsdanszky, Kalman [International Atomic Energy Agency, Dosimtery Section, Vienna (Austria)

1990-04-01

In 1968 at an IAEA meeting in Caracas, Venezuela, the dosimetric requirements of radiotherapy centres were discussed. At that time many radiotherapy departments in developing countries did not have a dosimeter. Even those that had a dosimeter were seldom able to send it to a Primary Standard Dosimetry Laboratory (PSDL) for proper calibration. The establishment of regional dosimeter calibration laboratories was recommended by the participating experts including representatives of WHO. There was general consent that it was not necessary to establish in every country a PSDL, which would need a very qualified staff and sophisticated equipment. Instead, the establishment of Secondary Standard Dosimetry Laboratories (SSDLs) was found to be an adequate solution to the problem. The new idea of SSDLs and their role within the international metrology system was thoroughly discussed at a joint IAEA/WHO meeting in Rio de Janeiro (scientific secretaries: H.H. Eisenlohr, IAEA and W. Seelentag, WHO) in December 1974. Considering the fact that an SSDL cannot work in isolation the experts recommended the setting up of an international Network of SSDLs under the auspices of the IAEA and WHO. The statutes of the IAEA/WHO Network of SSDLs were laid down in a Working Arrangement between the IAEA and WHO in April 1976. Later in 1976 the two Directors General of the IAEA and WHO formally announced by circular letters to their respective member states the establishment of the IAEA/WHO Network of SSDL. The Criteria for the Establishment of a Secondary Standard Dosimetry Laboratory were formulated by an Advisory Group and were attached to these letters. At that time there existed already 8 laboratories, which had been designated by WHO during the period 1968-1976 as regional reference centres for dosimetry. Another SSDL had been set up in Rio de Janeiro in collaboration between the Brazilian Government, the Government of the Federal Republic of Germany, and the IAEA. As a consequence of the

Comparison of the General Electric BWR/6 standard plant design to the IAEA NUSS codes and guides

International Nuclear Information System (INIS)

D'Ardenne, W.H.; Sherwood, G.G.

1985-01-01

The General Electric BWR/6 Mark III standard plant design meets or exceeds current requirements of published International Atomic Energy Agency (IAEA) Nuclear Safety Standards (NUSS) codes and guides. This conclusion is based on a review of the NUSS codes and guides by General Electric and by the co-ordinated US review of the NUSS codes and guides during their development. General Electric compared the published IAEA NUSS codes and guides with the General Electric design. The applicability of each code and guide to the BWR/6 Mark III standard plant design was determined. Each code or guide was reviewed by a General Electric engineer knowledgeable about the structures, systems and components addressed and the technical area covered by that code or guide. The results of this review show that the BWR/6 Mark III standard plant design meets or exceeds the applicable requirements of the published IAEA NUSS codes and guides. The co-ordinated US review of the IAEA NUSS codes and guides corroborates the General Electric review. In the co-ordinated US review, the USNRC and US industry organizations (including General Electric) review the NUSS codes and guides during their development. This review ensures that the NUSS codes and guides are consistent with the current US government regulations, guidance and regulatory practices, US voluntary industry codes and standards, and accepted US industry design, construction and operational practices. If any inconsistencies are identified, comments are submitted to the IAEA by the USNRC. All US concerns submitted to the IAEA have been resolved. General Electric design reviews and the Final Design Approval (FDA) issued by the USNRC have verified that the General Electric BWR/6 Mark III standard plant design meets or exceeds the current US requirements, guidance and practices. Since these requirements, guidance and practices meet or exceed those of the NUSS codes and guides, so does the General Electric design. (author)

The IAEA Standards for the Radioactive Discharge Control: Present Status and Future Development

International Nuclear Information System (INIS)

Balonov, M.; Linsley, G.; Robinson, C.; Cabianca, T.

2004-01-01

The International Atomic Energy Agency (IAEA) is the organization within the UN family with a statutory mandate to establish standards for the protection of health and environment against ionizing radiation, and to provide for the application of those standards. As part of these functions, the IAEA periodically reviews the status and continued relevance of the standards to the needs of its Member States. Recent work on the development of standards for the radioactive discharge control includes development of practical guidance for setting discharge limits, elaboration on methodology for the radiation protection of non-human species, and preparation of guidance on environmental monitoring for radiation protection purposes. Development of these safety documents is influenced by recent international and regional tendencies, based on social initiatives, to reduce radioactive discharges substantially below levels justified by radiological criteria. The IAEA has developed preliminary guidance on practical aspects of setting discharge limits, which included a review of national regulatory experience in this regard. This review suggested that societal pressures and regulatory practicalities results in discharge controls that were likely to be more restrictive that those that would be implied by formal optimization techniques. Regulatory review of authorizations includes a number of considerations, including predicted doses to members of the critical group, but the suitability of abatement forms a greater part in the decision-making process than allowed for in previous safety guidance. The IAEA has, in recent years, established a programme of work specifically addressing the development of safety standards on assessing the impact of ionizing radiation on non-human species, in co-operation with other relevant international organizations. The main issues arising will be summarised in the paper with the main focus on an exploration of the possible form of future regulatory

Standards for radiation protection and diagnostic radiology at the IAEA Dosimetry Laboratory

International Nuclear Information System (INIS)

Pernicka, F.; Andreo, P.; Meghzifene, A.; Czap, L.; Girzikowsky, R.

1999-01-01

International standardization in dosimetry is essential for the successful exploitation of radiation technology. The IAEA dosimetry programme is focused into services provided to Member States through the IAEA/WHO Network of Secondary Standard Dosimetry Laboratories (SSDLs), to radiotherapy centres and radiation processing facilities. Radiation protection quantities defined by ICRU and ICRP are used to relate the risk due to exposure to ionizing radiation to a single quantity, irrespective of the type of radiation, which takes into account the human body as a receptor. Two types of quantities, limiting and operational, can be related to basic physical quantities which are defined without need for considering specific aspects of radiation protection, e.g. air kerma for photons and fluence for neutrons. The use of a dosimeter for measurements in radiation protection requires a calibration in terms of a physical quantity together with a conversion from physical into protection quantities by means of a factor or a coefficient

An overview analysis of IAEA standard problem exercises

International Nuclear Information System (INIS)

Parzer, I.; Mavko, B.; Petelin, S.

1992-01-01

The modelling of some loss-of-coolant accident tests (IAEA-SPE), performed on the PMK-NVH integral test facility, have been studied in the present paper. A universal RELAP5 model of the facility has been developed at IJS, first for RELAP5/MOD2 and later upgraded for RELAP5/MOD3 use. To verify the modelling and determine the important details in the model, a nodalization study has been performed on the case of IAEA-SPE-2 experiment. In parallel MOD2 and MOD3 capabilities of modelling highly non-equilibrium processes, as took place in IAEA-SPE-2 experiment, have been compared. Using the most detailed of the developed models, the capabilities of both code versions have been compared on the case of IAEA-SPE-1 and 2 (Small Break Loss-of-Coolant Accidents - SB LOCAs) and IAEA-SPE-3 (Steam Generator Tube Rupture - SGTR), adapted only accordingly to the three SPE experiment arrangements. The calculations nave been performed with RELAP5/MOD2/36.05 and MOD3 5m5 code versions on a VAX 4000-200 computer. (author)

IAEA safety glossary. Terminology used in nuclear safety and radiation protection, multilingual 2007 edition, including the IAEA safety fundamentals [no. SF-1

International Nuclear Information System (INIS)

2008-10-01

The IAEA Safety Glossary defines and explains technical terms used in the IAEA Safety Standards and other safety related IAEA publications, and provides information on their usage.The publication is multilingual and covers the six official IAEA languages,, Arabic, Chinese, English, French, Russian and Spanish. It has been in use since April 2000. The 2007 Edition is a revised and updated version. The primary purpose of the publication is to harmonize terminology and usage in the IAEA Safety Standards. It is a source of information for users of the IAEA Safety Standards and other safety related IAEA publications and provides guidance for the drafters and reviewers of publications, including IAEA technical officers and consultants, and members of technical committees, advisory groups, working groups and bodies for the endorsement of safety standards

IAEA nuclear data for applications: Cross section standards and the reference input parameter library (RIPL)

International Nuclear Information System (INIS)

Capote Noy, Roberto; Nichols, Alan L.; Pronyaev, Vladimir G.

2003-01-01

An integral part of the activities of the IAEA Nuclear Data Section involves the development of nuclear data for a wide range of user applications. When considering low-energy nuclear reactions induced by neutrons, photons and charged particles, a detailed knowledge is required of the production cross sections over a wide energy range, spectra of emitted particles and their angular distributions. Two highly relevant IAEA data development projects are considered in this paper. Neutron reaction cross-section standards represent the basic quantities needed in nuclear reaction cross-section measurements and evaluations. These standards and the covariance matrices of their uncertainties were previously evaluated and released in 1987. However, the derived uncertainties were subsequently considered to be unrealistic low due to the effect of the low uncertainties obtained in fitting the light element standards to the R-matrix model; as a result, evaluators were forced to scale up the uncertainties to 'expected values'. An IAEA Coordinated Research Project (CRP) entitled 'Improvement of the Standard Cross Sections for Light Elements' was initiated in 2002 to improve the evaluation methodology for the covariance matrix of uncertainty in the R-matrix model fits, and to produce R-matrix evaluations of the important light element standards. The scope of this CRP has been substantially extended to include the preparation of a full set of evaluated standard reactions and covariance matrices of their uncertainties. While almost all requests for nuclear data were originally addressed through measurement programmes, our theoretical understanding of nuclear phenomena has reached a reasonable degree of reliability and nuclear modeling has become standard practice in nuclear data evaluations (with measurements remaining crucial for data testing and benchmarking). Since nuclear model codes require a considerable amount of numerical input, the IAEA has instigated extensive efforts to

Instant standard concept for data standards development

NARCIS (Netherlands)

Folmer, Erwin Johan Albert; Kulcsor, Istvan Zsolt; Roes, Jasper

2013-01-01

This paper presents the current results of an ongoing research about a new data standards development concept. The concept is called Instant Standard referring to the pressure that is generated by shrinking the length of the standardization process. Based on this concept it is estimated that the

The International Atomic Energy Agency (IAEA) standards and recommendations on radioactive waste and transport safety

International Nuclear Information System (INIS)

Warnecke, E.; Rawl, R.

1996-01-01

The International Atomic Energy Agency (IAEA) publishes standards and recommendations on all aspects of nuclear safety in its Safety Series, which includes radioactive waste management and transport of radioactive materials. Safety Series documents may be adopted by a State into its national legal framework. Most of the States used the IAEA transport regulations (Safety Series No. 6) as a basis for their national regulation. The two highest ranking documents of the Radioactive Waste Safety Standards (RADWASS) programme, the Safety Fundamentals and the Safety Standard on the national waste management system, have been published. Both provide impetus into the waste management safety convention, a legally binding document for signatory states, which is being drafted. The already existing Convention on Nuclear Safety covers the management of radioactive waste at land-based civil nuclear power plants. (author) 1 fig., 18 refs

Referring to IAEA system to improve Chinese standards system on nuclear and radiation safety

International Nuclear Information System (INIS)

Shang Zhaorong; Wang Wenhai

2010-01-01

Referring to the standards system of IAEA, to build and improve the Chinese standards system of nuclear and radiation safety is a long term infrastructure work and an assurance to keep sustainable development of nuclear industry and nuclear technology application in China. The paper analyses the current main problem, and gives some suggestions on developing and improving the system. (authors)

IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

International Nuclear Information System (INIS)

2007-01-01

In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAEA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

International Nuclear Information System (INIS)

2007-06-01

In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAEA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

International Nuclear Information System (INIS)

2007-01-01

In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

The IAEA inspectorate, including new requirements

International Nuclear Information System (INIS)

Alston, W.

1998-01-01

The basic purpose of the IAEA safeguards system is 'timely detection of diversion of significant quantities of nuclear material'. Safeguards implementation is regulated by the IAEA Statute and individual safeguards agreements. The IAEA Inspectorate and its scope are described together with the technical objectives and the concept of verification. Effective implementation of safeguards requires cooperation between the IAEA and the state concerned. To this end, agreements require that the State should establish and maintain a system of accounting for and control of nuclear material subject to safeguards. The IAEA safeguards system has demonstrated a flexibility capable of responding to the verification demands of Member States. Is is capable of safeguarding nuclear materials, facilities, equipment and non-nuclear material. The IAEA is in the process of strengthening safeguards in its verification of declared activities

The IAEA inspectorate, including new requirements

Energy Technology Data Exchange (ETDEWEB)

Alston, W [International Atomic Energy Agency, Department of Safeguards, Division of Operations A, Vienna (Austria)

1999-12-31

The basic purpose of the IAEA safeguards system is `timely detection of diversion of significant quantities of nuclear material`. Safeguards implementation is regulated by the IAEA Statute and individual safeguards agreements. The IAEA Inspectorate and its scope are described together with the technical objectives and the concept of verification. Effective implementation of safeguards requires cooperation between the IAEA and the state concerned. To this end, agreements require that the State should establish and maintain a system of accounting for and control of nuclear material subject to safeguards. The IAEA safeguards system has demonstrated a flexibility capable of responding to the verification demands of Member States. Is is capable of safeguarding nuclear materials, facilities, equipment and non-nuclear material. The IAEA is in the process of strengthening safeguards in its verification of declared activities

A Little Customs Glossary for IAEA Safeguards: Customs Procedures and Concepts that Matter for the Implementation of Modern Safeguards

Energy Technology Data Exchange (ETDEWEB)

Chatelus, Renaud [Consultant, Export Control and IAEA Safeguards Specialist, IAEA (International Atomic Energy Agency (IAEA))

2012-06-15

The additional protocols to the IAEA comprehensive safeguards agreements include provisions about the reporting by states of their imports and exports of listed equipment and non-nuclear material, also known as the 'trigger list', as well as nuclear materials. Beyond declarations and their verification, IAEA Safeguards also looks at other Imports and exports as part of its efforts to build confidence on the absence of undeclared nuclear activities or material. In all cases, information about international transfers of interest to Nuclear Safeguards is closely related to export control activities. But, if much has been written about the material and equipment to be declared, neither IAEA Safeguards nor Export control related documents provide much explanation about what exports and imports actually are. In fact, precise legal definitions are to be found generally in national customs regulations and international agreements on customs and trade. Unfortunately, these are not necessarily in line with Safeguards understanding. It is therefore essential that IAEA safeguards comprehends the customs concepts and procedures that are behind Safeguards relevant information.

A Little Customs Glossary for IAEA Safeguards: Customs Procedures and Concepts that Matter for the Implementation of Modern Safeguards

International Nuclear Information System (INIS)

Chatelus, Renaud; )

2012-01-01

The additional protocols to the IAEA comprehensive safeguards agreements include provisions about the reporting by states of their imports and exports of listed equipment and non-nuclear material, also known as the “trigger list”, as well as nuclear materials. Beyond declarations and their verification, IAEA Safeguards also looks at other Imports and exports as part of its efforts to build confidence on the absence of undeclared nuclear activities or material. In all cases, information about international transfers of interest to Nuclear Safeguards is closely related to export control activities. But, if much has been written about the material and equipment to be declared, neither IAEA Safeguards nor Export control related documents provide much explanation about what exports and imports actually are. In fact, precise legal definitions are to be found generally in national customs regulations and international agreements on customs and trade. Unfortunately, these are not necessarily in line with Safeguards understanding. It is therefore essential that IAEA safeguards comprehends the customs concepts and procedures that are behind Safeguards relevant information.

The dosimetry programme of the IAEA

International Nuclear Information System (INIS)

1987-01-01

Describes the activities of the IAEA's Dosimetry Laboratory which provides calibration and comparison services for secondary standard dosimetry laboratories (SSDLs) of Member States. In addition, a joint IAEA/WHO postal dosimetry service has been established for radiotherapy centers. The International Measurement System and the calibration ''chain'' from measurement standard instruments of the International Bureau of Weights and Measurements (BIPM) through the primary and secondary standards to the dosimeters of the users are presented as well

The reinterpretation of standard deviation concept

OpenAIRE

Ye, Xiaoming

2017-01-01

Existing mathematical theory interprets the concept of standard deviation as the dispersion degree. Therefore, in measurement theory, both uncertainty concept and precision concept, which are expressed with standard deviation or times standard deviation, are also defined as the dispersion of measurement result, so that the concept logic is tangled. Through comparative analysis of the standard deviation concept and re-interpreting the measurement error evaluation principle, this paper points o...

Comparison between IAEA GS-R-3 and ISO 9001:2000

International Nuclear Information System (INIS)

Biscan, R.

2008-01-01

International Atomic Energy Agency (IAEA) developed Safety Standard 'The Management System for Facilities and Activities' (GS-R-3) to define the requirements for establishing, implementing, assessing, and continually improving an integrated management system to integrate: safety, health, environmental, security, quality and economic elements. Standard requirements must be met to ensure the protection of people and the environment and they are governed by the objectives, concepts and IAEA Safety Fundamentals principles. The GS-R-3 requirements may be used as the basis for the: Management System of organizations directly responsible for operating facilities and activities and providing services; Regulation of these facilities and activities by the regulatory body: Management System of the relevant regulatory bodies; Operator, to specify to the supplier, via contractual documentation, any specific requirements that must be included in the supplier's management system for the supply and delivery of products. International Organization for Standardization (ISO) developed International Standard 'Quality Management Systems - Requirements' (ISO 9001:2000) to specify requirements for a quality management system where an organization: Needs to demonstrate its ability to consistently provide product that meets customer and applicable regulatory requirements, and Aims to enhance customer satisfaction through the effective application of the system, including processes for continual improvement of the system and the assurance of conformity to customer and applicable regulatory requirements. IAEA GS-R-3 is focused on meeting the overall safety requirements for the plant, personnel and society in general, and grading the application of the management system. Any State wishing to enter into an agreement with the IAEA concerning any form of Agency assistance is required to comply with the requirements of this safety standard that pertain to the activities covered by the agreement

The concepts of exclusion, exemption and clearance as used in the interagency basic safety standards and related IAEA documents

International Nuclear Information System (INIS)

Webbl, G.A.M.

1997-01-01

Mechanisms are needed to remove from regulatory control those exposures or radiation sources that do not warrant concern. In this paper three such conceptual mechanisms are examined from their historical development to their current usage in the Interagency Basic Safety Standards. These concepts are exclusion, applied to exposures that are not amenable to control, exemption applied in advance on the basis of low risks to prevent practices or sources from entering the regulatory control system, and clearance, a similar concept but used to remove sources from the regulatory control system. The application of and interrelationships between these concepts, is described. (author)

The role of the IAEA Dosimetry Laboratory in the dissemination of standards for radiation protection

International Nuclear Information System (INIS)

Czap, L.; Andreo, P.; Matscheko, G.

1998-01-01

Approximately 90% of the Secondary Standard Dosimetry Laboratories (SSDLs) provide users with calibrations of radiation protection instruments, and the IAEA is taking every necessary effort to insure that SSDLs measurements are traceable to Primary Standards. The Agency has proper radiation sources available to provide traceable calibrations to the SSDLs involved in measurements on diagnostic x-ray generators, including an x-ray unit specifically for mammography dedicated to standardization procedures. The different photon beam qualities and calibration procedures available in the Agency's Dosimetry Laboratory are described

The IAEA's role in safe radioactive waste management

International Nuclear Information System (INIS)

Flory, D.; Bruno, G.

2011-01-01

In accordance with its statute, IAEA is authorized to develop and maintain safety standards. This mission is reflected in the main programme of the IAEA on nuclear safety and security. In the field of the safety of radioactive waste management the IAEA is responsible for the delineation of a global safety regime to protect the public and the environment from harmful effects of ionizing radiation. This delineation is established on the basis of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, as well as on the development of safety standards for the management of all radioactive waste. The safety standards are the fruit of an international consensus on a high level of safety for the protection of people and environment. Safety guides are edited by IAEA, 7 volumes concern general safety requirements and 6 volumes deal with specific safety requirements (for instance for research reactors or for radioactive waste disposal facilities). Furthermore the IAEA assists Member States in the implementation of the safety standards and provides related services

The roles of Euratom and the IAEA in nuclear non-proliferation - a Euratom view

International Nuclear Information System (INIS)

Szymanski, P.

2013-01-01

The IAEA safeguards conclusion that all nuclear material has remained in peaceful activities in a State is based on the finding that there are no indications of diversion of declared nuclear material from peaceful activities and no indications of undeclared nuclear material or activities in the State as a whole. The state-level concept that has been introduced by the IAEA in this respect allows and obliges the IAEA to take into account state specific factors to determine the set of safeguards activities to be applied in a State. The effectiveness of the EURATOM regional safeguards systems, its cooperation with the IAEA and its independence from States and operators are among the factors which the IAEA needs to consider in order to apply safeguards in an effective and efficient way. Socio-economic and political factors like the support to international non-proliferation should also be factors in this concept. The intended evolution of the state-level concept by the IAEA then should result in making better use of the activities of EURATOM safeguards. This is possible by the IAEA relying more on the EURATOM activities for the verification of declared nuclear material and the IAEA concentrating on getting assurance on the absence of undeclared materials and activities. Developing a regional-level concept that supplements the state-level concept can contribute to determine the extent to which the IAEA can make better use of EURATOM safeguards in the future. (author)

Implementation of a management system in accordance with IAEA GS-R-3 Standard. A gap analysis

International Nuclear Information System (INIS)

Dicianu, I.; Oprea, M.

2009-01-01

Full text: The design and implementation of an Integrated Management System at SNN SA Headquarters become necessary as the CNCAN norms are already under revision to comply with the IAEA GS-R-3 standard. The purpose of this analysis is to draft a project for the transition from a Quality Management System (QMS) to an Integrated Management System (IMS) complying with GS-R-3 requirements. Four steps were identified for developing this project: STEP1 - To justify the necessity of the IMS implementation to meet the SNN SA Headquarters Top Management commitments. The requirements for implementing an IMS are analyzed and a comprehensive document is issued to (and maybe discussed with) SNN General Director in order to obtain the top management adherence/commitment to the project implementation. The document will show the strong and the weak points which should be considered in developing the project. The references for the project are: - IAEA Safety Standard GS-R-3 'The Management System for Facilities and Activities'; - ISO - 1400/2004 Standard 'Environmental Management System Requirements'; - OHSAS 18001/2007 Standard 'Occupational Health and Safety Management Systems. Requirements'; There are also considered: - IAEA Safety Guide GS-G-3.1 'Application of the Management System for Facilities and Activities'; - IAEA Draft Safety Guide DS-349 'Application of the Management System for Nuclear Facilities; There will be considered: Workshop 2 Bookmarks (F5) 2 - CNCAN Norms (as they will be revised); STEP2 - The performance of a comparative analysis of the requirements of GS-R-3, ISO 14001 and OHSAS 18001 versus the provisions of the QMS already implemented in SNN. This analysis is shown as a comparative table; STEP3 - Identification of the IMS processes. An overall analysis of the current processes described in the SNN QMS Manual is performed and based on this. There are identified the additional processes that have to be documented for the proper implementation of an IMS

Progress report on the IAEA programme on the standardization of reactor dosimetry measurements

International Nuclear Information System (INIS)

Ertek, C.; Cross, B.; Chernyshev, V.

1979-01-01

This report briefly summarizes present activities, current status and procedures associated with neutron spectrum unfolding by activation technique within the IAEA programme on standardization of reactor radiation measurements. Experimental efforts and calculations related to unfolding are critically analyzed including the most recent techniques, interlaboratory cooperation, direct influence of recently measured cross-sections on the unfolded neutron flux density spectrum, re-evaluation of some cross-sections, neutron self-shielding factors and scattering effects. (author)

IAEA concerns about advanced containment and surveillance concepts or other alternative safeguards concepts

International Nuclear Information System (INIS)

von Baeckmann, A.; Powers, J.

1981-01-01

Nuclear material accountancy is used in IAEA safeguards as a measure of fundamental importance, with containment and surveillance as important complementary measures. Over the past five years the IAEA has worked with its Standing Advisory Group on Safeguards Implementation (SAGSI) to quantify major terms of the objectives, i.e., timeliness of detection, significant quantities and detection probabilities. The Agency is using those quantifications, as recommended by SAGSI, as guidelines for inspection planning and for evaluating the effectiveness of safeguards. The guidelines are used in this paper, together with other criteria like cost-effectiveness, compliance with legal limitation and non-intrusiveness, as yard-sticks for the assessment of the potential capabilities of alternative safeguards approaches. 4 refs

Integrated management system - management standards evolution and the IAEA new approach

International Nuclear Information System (INIS)

Oliveira, Dirceu Paulo de; Zouain, Desiree Moraes

2007-01-01

The management standards application began in military and nuclear areas towards the end of Second World War, when some westerns countries developed quality standards to improve their means to assess suppliers' conditions to assure their products conformance, which was increasingly complex and required a higher degree of reliability. Afterwards, the quality standards application was extended to the consumer market focused on consumers' requirements satisfaction. Coming along the society crescent concern about quality of life, other management standards were developed, such as those dealing with environmental and sustainable development, occupational health and safety, social accountability and so on. As a consequence, the management process became complex. The management system integrated form approach makes possible the compatibility of distinct and complementary interests from several functions and disciplines involved and supply the absence of the organizations' holistic approach. According to this integrated management approach, the Agency - 'International Atomic Energy Agency' (IAEA) - decided to review the structure of the 50-C-Q standard - 'Quality Assurance for Safety in Nuclear Power Plants and Other Nuclear Installations', from 1996, publishing in 2006 the new GS-R-3 standard - 'The Management System for Facilities and Activities - Safety Requirements'. This work presents a brief evolution of management standards and integrated management approach, showing the Agency's new vision concerning this issue with the GS-R-3 standard publication. (author)

On IAEA's role in radiation protection, with focus on Africa

International Nuclear Information System (INIS)

Mansoux, H.

2010-01-01

The safety functions of IAEA are to establish standards of radiation safety, to provide for the application of international standards and to facilitate and service international conventions and other undertakings. The IAEA Safety Standards are: . Not binding on Member States but may be adopted by them. . Binding for IAEA.s own activities. . Binding on States in relations to operations assisted by the IAEA. . Binding on States wishing to enter into project agreements with IAEA. The Categories of the Standards are:- 8 - Safety Fundamentals: Set out principles for protecting people and the environment - Safety Requirements: Establish requirements: what has to be done (.shalls.) to apply these principles in meeting objectives - Safety Guides: Set out recommended ways (.shoulds.) of meeting the requirements IAEA Process Flow for the Development of IAEA The Overall Priorities of IAEA are to:- . Setting high quality safety standards & promoting their wider use and application; . Maintain current level of use of IAEA peer reviews and advisory services by Member States; . Encourage wide adherence to the international instruments such as the Code of Conduct on safety and security of radioactive sources and the Joint Convention on the safety of spent fuel management and safety of radioactive waste management; . Develop capabilities for capacity building in safety, including creation of reference training centres for education in radiation safety. Challenges for IAEA include:- Future expections Uranium industry Protection of the environment Increased use of radioactive sources Medical application Trans-boundary movement of radioactive material Scientific challenges in radiation protection Needs in radiation protection bases Role of IAEA on radiation protection bases

Correspondence of ISO 9001:2008 with IAEA GS-R-3

International Nuclear Information System (INIS)

Kibrit, Eduardo

2009-01-01

This article identifies, characterises and analyses International Organisation for Standardisation (ISO) and International Atomic Energy Agency (IAEA) normative requirements for the development and implementation of quality management systems in nuclear organisations. The structures of the applicable standards, ISO 9001:2008 and IAEA GS-R-3, are characterised. The differences and similarities of objective, focus, scope, level of application, structure, vocabulary, management system, management responsibility, resource management, process implementation, measurement, assessment and improvement verified in the applicable standards are deeply reviewed. A correspondence of the applicable standards' requirements is presented topic by topic. A correlation of the applicable standards' requirements is made, showing IAEA GS-R-3 topics that have no correlation with ISO 9001:2008 and ISO 9001:2008 topics that have no correlation with IAEA GS-R-3. Conclusive remarks advise the pros and cons of using one of the applicable standards or the other. (author)

Japanese contributions to IAEA INTOR workshop, phase two A, part 2, chapter XI: concept evolution, chapter XII: design concept, and chapter XIII: operation and test programme

International Nuclear Information System (INIS)

Tomabechi, Ken; Fujisawa, Noboru; Iida, Hiromasa

1985-07-01

This report corresponds to Chapters XI, XII, and XIII of Japanese contribution report to IAEA INTOR Workship, Phase Two A, Part 2. In the phase Two A, Part 2 workshop, we have studied critical technical issues and have also assessed scientific and technical data bases. Based on those results, the INTOR design have been modified to upgrade the design concept. The major modification items are related to plasma beta value, plasma operation scenario, reactor size reduction, neutron fluence, tritium producing blanket, and implementation of active control coils. In those chapters, the concept evolution for the design modification and main results are described. (author)

A preliminary comparative study on the content of cesium, thorium and uranium in IAEA standard reference material

International Nuclear Information System (INIS)

Zhang Jing; Liu Husheng; Wang Xiaoyan; Wang Naifen

2000-01-01

This paper presents the detection of Cs, Th and U in 6 standard reference materials provided by IAEA, using the ICP-MS method. The bismuth (Bi) was selected as internal standard element for the range compensation of matrix inhibitory effect and flow of the sensibility. The detection limit of the 3 elements was limited in the range of 0.0006∼2ng/ml, 0.4∼0.5g sample was taken and digested by acid, and detected directly by ICP-MS. The recovery of standard addition was 82.1∼100.1%

The present status of IAEA safeguards on nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1978-11-01

The present IAEA approach to safeguarding various types of nuclear facilities is examined. The IAEA safeguards objectives, criteria and specific techniques are addressed, with reference e.g. to concepts like timely detection, quantities of safeguards significance, and conversion times. Material accountancy and containment and surveillance as basic features of IAEA safeguards verification are discussed. Safeguards measures for specific facility types are considered and corresponding levels of IAEA safeguards experience are assessed. Outlines of expected IAEA safeguard approaches to large bulk handling facilities are discussed. The evolutionary nature of safeguards based on experience and research and development is mentioned

An application of the IAEA GCS-R-3 Standard in Nuclear Quality Management System

Energy Technology Data Exchange (ETDEWEB)

Kim, D. I.; Juhn, P. E. [TUEV SUED Korea, Seoul (Korea, Republic of); Kwon, M. J. [TUEV SUED KOCEN, Seoul (Korea, Republic of)

2012-03-15

IAEA GCS-R-3 Standard (2006) is intended to help nuclear community establishing a nuclear quality management system that integrates such 6 elements as safety, health, environment, security, quality and economics. In the present paper, the management principles of GCS-R-3 Standard are compared with those of ISO 9001 and ASME N/A-1 Codes and Standards. The paper also summarizes the worldwide survey on application of GS-R-3, which was conducted by the TUEV SUED Korea in 2011. The result concludes that the top priority should be given to safety upon which the management system must be based, in proper coordination with other 5 elements to enhance nuclear safety, in particular after Fukushima Dais-Ici nuclear power accidents on 11{sup th} March 2011 in Japan.

Role of the IAEA in the radiological protection of patients

International Nuclear Information System (INIS)

Ortiz Lopez, P.; Wrixon, A.D.; Meghzifene, A.; Izewska, J.

2001-01-01

The paper discusses the role of the IAEA in relation to the radiological protection of patients. Within the IAEA there are two major programmes which have an impact on the protection of the patient. Firstly, patient protection is part of the programme on radiation safety; secondly, the human health programme contains a number of activities related to quality assurance (QA), and these also contribute to the protection of patients. A function of the IAEA, as stipulated in its Statute, is 'to establish or adopt, in consultation and, where appropriate, in collaboration with the competent organs of the United Nations and with the specialized agencies concerned, standards of safety for protection of health and minimization of danger to life and property' and to provide for the application of these standards...'. There are three different levels of the IAEA Safety Standards: Safety Fundamentals, Safety Requirements and Safety Guides. The Standards are supported by other documents such as Safety Reports. There are five means used by the IAEA in providing for the application of the Standards: co-ordinating research, promoting education and training, providing assistance, fostering information exchange and rendering services to its Member States. All these means are used in the programme on radiological protection of patients as described in the paper. The IAEA is assisting its Member Sates in the development and implementation of QA programmes. These activities help disseminate not only the technical knowledge but also the basic ingredients of the QA culture. The IAEA assistance is directed at: (1) national regulatory bodies for the establishment of a regulatory framework which complies with the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; (2) standards laboratories for metrological traceability; and (3) end users at medical institutions for the development and implementation of QA programmes

IAEA research coordination meeting on X- and gamma-ray standards for detector efficiency calibration, Braunschweig, FRG, 31 May - 2 June 1989. Summary report

International Nuclear Information System (INIS)

Christmas, P.; Nichols, A.L.; Lemmel, H.D.

1989-07-01

The final official meeting of the IAEA Coordinated Research Programme on the Measurement and Evaluation of X- and Gamma-ray Standards for Detector Efficiency Calibration was held in Braunschweig from 31 May to 2 June 1989. Work undertaken by the participants was reviewed in detail, and actions were agreed to resolve specific issues and problems. Initial steps were also made to establish a format and procedure for the preparation by mid-1990 of an IAEA Technical Reports Series booklet; the measurements and recommended data will be listed, and an IAEA data file established for issue to all interested organisations. (author). 3 tabs

The international dimensions of nuclear safety standards

International Nuclear Information System (INIS)

Reed, J.M.

1992-01-01

The paper reviews the activities of the major international organisations in the field of nuclear safety standards; the International Atomic Energy Agency (IAEA), the OECD's Nuclear Energy Agency (NEA) and the Commission of the European Communities. Each organisation encourages the concept of international nuclear safety standards. After Chernobyl, there were calls for some form of binding international nuclear safety standards. Many Member States of IAEA accepted these Codes as a suitable basis for formulating their national safety standards, but the prevailing view was that voluntary compliance with the Codes was the preferred path. With few reactor vendors in a limited international market, the time may be approaching when an internationally licensable nuclear reactor is needed. Commonly accepted safety standards would be a prerequisite. The paper discusses the issues involved and the complexities of standards making in the international arena. (author)

The IAEA programme on research reactor safety

International Nuclear Information System (INIS)

Abou Yehia, H.

2007-01-01

According to the research reactor database of IAEA (RRDB), 250 reactors are operating worldwide, 248 have been shut down and 170 have been decommissioned. Among the 248 reactors that do not run, some will resume their activities, others will be dismantled and the rest do not face a clear future. The analysis of reported incidents shows that the ageing process is a major cause of failures, more than two thirds of operating reactors are over 30 years old. It also appears that the lack of adequate regulations or safety standards for research reactors is an important issue concerning reactor safety particularly when reactors are facing re-starting or upgrading or modifications. The IAEA has launched a 4-axis program: 1) to set basic safety regulations and standards for research reactors, 2) to provide IAEA members with an efficient help for the application of these safety regulations to their reactors, 3) to foster international exchange of information on research reactor safety, and 4) to provide IAEA members with a help concerning safety issues linked to malicious acts or sabotage on research reactors

Combined approach of grey relational analysis and analytic hierarchy process for ARCAL/IAEA strategic actions prioritization

International Nuclear Information System (INIS)

Silva, Pedro Maffia da; Martins, Eduardo Ferraz; Rondinelli Junior, Francisco; Garcia, Pauli Adriano de Almada

2015-01-01

The IAEA technical cooperation (TC) programme is the main mechanism through which the IAEA delivers technical services to its Member States. Through the programme, the IAEA helps Member States to build, strengthen and maintain capacities in the safe, peaceful and secure use of nuclear technology in support of sustainable socioeconomic development. The Regional Cooperation Agreement for the Promotion of Nuclear Science and Technology in Latin America and the Caribbean (ARCAL) is a TC agreement between most IAEA member states in the Latin America and the Caribbean region for technical and economic cooperation to promote the use of nuclear techniques for peace and development. The present study aims to propose a combined approach to prioritize the needs and problems of ARCAL region. To do that, this paper considers the concept of Grey Relational Analysis and Analytic Hierarchy Process for data treatment, standardization and ranking of those needs and problems. In other words, the proposition intend to reduce the biases that may be introduced along the stage of the needs and problems assessment in the regional strategic profile formulation. (author)

Combined approach of grey relational analysis and analytic hierarchy process for ARCAL/IAEA strategic actions prioritization

Energy Technology Data Exchange (ETDEWEB)

Silva, Pedro Maffia da; Martins, Eduardo Ferraz; Rondinelli Junior, Francisco, E-mail: pmsilva@cnen.gov.br, E-mail: efmartins@cnen.gov.br, E-mail: rondinel@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Garcia, Pauli Adriano de Almada, E-mail: pauliadriano@id.uff.br [Universidade Federal Fluminense (UFF), Volta Redonda, RJ (Brazil)

2015-07-01

The IAEA technical cooperation (TC) programme is the main mechanism through which the IAEA delivers technical services to its Member States. Through the programme, the IAEA helps Member States to build, strengthen and maintain capacities in the safe, peaceful and secure use of nuclear technology in support of sustainable socioeconomic development. The Regional Cooperation Agreement for the Promotion of Nuclear Science and Technology in Latin America and the Caribbean (ARCAL) is a TC agreement between most IAEA member states in the Latin America and the Caribbean region for technical and economic cooperation to promote the use of nuclear techniques for peace and development. The present study aims to propose a combined approach to prioritize the needs and problems of ARCAL region. To do that, this paper considers the concept of Grey Relational Analysis and Analytic Hierarchy Process for data treatment, standardization and ranking of those needs and problems. In other words, the proposition intend to reduce the biases that may be introduced along the stage of the needs and problems assessment in the regional strategic profile formulation. (author)

Building a stronger framework of nuclear law. The IAEA's legislative assistance services

International Nuclear Information System (INIS)

Stoiber, C.

2003-01-01

The IAEA is publishing a Handbook on Nuclear Law which will provide IAEA Member States with a new resource for assessing the adequacy of their national legal frameworks governing the peaceful uses of nuclear energy; and practical guidance for governments in efforts to enhance their laws and regulations, in harmonizing them with internationally recognized standards, and in meeting their obligations under relevant international instruments. The Handbook responds to the growing demand from many national governments for assistance in the development of nuclear legislation and the need to harmonize their own legal and institutional arrangements with international standards. It also presents concise and authoritative instructional materials for teaching professionals (lawyers, scientists, engineers, health and radiation protection workers, government administrators) on the basic elements of a sound framework for managing and regulating nuclear energy. The Handbook is organized into five general parts: Part I provides a general overview of key concepts in the field: nuclear energy law and the legislative process; the regulatory authority; and the fundamental regulatory activities of licensing, inspection and enforcement. Part II deals with radiation protection. Part Ill covers various subjects arising from nuclear and radiation safety: radiation sources, nuclear installations, emergency preparedness and response, mining and milling, transportation, and waste and spent fuel. Part IV addresses the topic of nuclear liability and coverage. Part V moves to non-proliferation and security related subjects: safeguards, export and import controls, and physical protection. The Handbook also reflects and refers to the extensive range of IAEA Safety Standards covering all fields relevant to peaceful nuclear technology

Input data preparation and simulation of the second standard problem of IAEA using the Trac/PF1 code

International Nuclear Information System (INIS)

Madeira, A.A.; Pontedeiro, A.C.; Silva Galetti, M.R. da; Borges, R.C.

1989-10-01

The second Standard Problem sponsored by IAEA consists in the simulation of a small LOCA located in the downcomer of a PMK-NVH integral test facility, which models WWER/440 type reactor. This report presents input data preparation and comparison between TRAC-PF1 results and experimental measurements. (author) [pt

FORATOM - IAEA Workshop, Mamaia 2006

International Nuclear Information System (INIS)

Florescu, Nicolai

2006-01-01

The FORATOM Workshop was organized on May 16-19, 2006 by IAEA and FORATOM in the frame of common actions of experience exchange planned to take place every 18 months. At the same time at Mamaia, Romania, a meeting of the Business Excellence FORATOM group took place in which the Romanian organization ROMATOM is represented by the author of the paper from behalf of the Quality Management Group. Romanian Atomic Forum, ROMATOM as a member of European Atomic Forum, FORATOM, plays an active role in nuclear field in Romania. The Business Excellence Working Group, as the most active group in FORATOM, has the following objectives: - to promote and support the safe and effective performance of nuclear facilities to encourage the common of high level business standards; - to support FORATOM to enable decision makers and the public at large to get informed; - to facilities the exchange of best practices for management systems in order to raise the level of awareness and understanding so that members can better support the improvement within the member organizations, the other nuclear facilities in the BEx -WG member countries, the regular organization in the member countries, and international organizations active in the same fields of interest; - to provide a focus for influencing the development and harmonization of nuclear industry standards and practices to achieve improved business effectiveness and quality and safety management of nuclear facilities; - to advise FORATOM on management system issues. The FORATOM Workshop organized at Mamaia was held under the topics 'Successful Management of Organizational Change'. Three key issues for debate were established as follows: - key issue 1, effective handling of organizational change: drivers for change; managing change: the IAEA perspective; managing change within a utility; managing outsourcing; - key issue 2, organizational culture and safety culture: management systems and safety culture; proactive management; developing

Stress Tests Worldwide - IAEA Nuclear Safety Action Plan

International Nuclear Information System (INIS)

Lyons, J.E.

2012-01-01

The IAEA nuclear safety action plan relies on 11 important issues. 1) Safety assessments in light of the Fukushima accident: the IAEA secretariat will develop a methodology for stress tests against specific extreme natural hazards and will provide assistance for their implementation; 2) Strengthen existing IAEA peer reviews; 3) Emergency preparedness and response; 4) National Regulatory bodies in terms of independence and adequacy of human and financial resources; 5) The development of safety culture and scientific and technical capacity in Operating Organizations; 6) The upgrading of IAEA safety standards in a more efficient way; 7) A better implementation of relevant conventions concerning nuclear safety and nuclear accidents; 8) To provide a broad assistance on safety standard for countries embarking on a nuclear power program; 9) To facilitate the use of available information, expertise and techniques concerning radiation protection; 10) To enhance the transparency of nuclear industry; and 11) To promote the cooperation between member states in nuclear safety. (A.C.)

IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Working Material

International Nuclear Information System (INIS)

2013-01-01

In response to needs expressed by Member States and within a broader IAEA-wide effort in nuclear knowledge preservation, the IAEA has been carrying out a dedicated initiative on Fast Reactor Data Knowledge Preservation (FRKP). The main objectives of the FRKP initiative are to: • Halt the on-going loss of information related to Fast Reactors (FR); • Collect, retrieve, preserve and make accessible already existing data and information on FR. These objectives require the implementation of activities supporting digital document archival, exchange, search and retrieval and facilitating, by developing and using suitable standards and IT tools, the knowledge preservation over the next decades. To this purpose the IAEA has developed the Fast Reactor Knowledge Organization System (FRKOS), a web-based application employing IAEA methodology and approach for categorization of FR knowledge domain, which allows creating a comprehensive and well-structured international inventory of fast reactor data and information provided by different Member States. The resulting Web Portal is established and maintained by the IAEA. The IAEA knowledge preservation initiatives and tools in the field of fast neutron systems - which were presented and very well received during the recent IAEA Fast Reactor and Related Fuel Cycles Conference (FR13) - are supposed to be of interest for national nuclear authorities, regulators, scientific and research organizations, commercial companies and all other stakeholders involved in fast reactor activities at national or international level. The objectives of the technical meeting were to: • Exchange information between the member states/international organizations on national and international initiatives addressing knowledge preservation and data retrieval/collection in the field of fast neutron systems; • Present and discuss the member states’/international organizations’ policies and conditions for releasing to the IAEA both publicly

Appraisal for France of the safety of the transport of radioactive material. Provision for the application of the IAEA safety standards

International Nuclear Information System (INIS)

2004-01-01

The IAEA has the specific statutory function within the United Nations system of establishing standards of safety for the protection of health against exposure to ionizing radiation. As part of this mandate, the IAEA has issued Regulations for the Safe Transport of Radioactive Material, and has also established the Transport Safety Appraisal Service (TranSAS) to carry out, at the request of States, appraisals of the implementation of these regulations. The IAEA carried out such an appraisal in France from 27 March to 8 April 2004. The appraisal addressed all relevant transport activities in France, both national and international, for all modes of transport, with special emphasis on the maritime transport and air transport of radioactive material. This report summarizes the findings of the 13 independent experts who participated in the appraisal

Beam quality dependence of IAEA TLDs irradiated in a standardized geometry

International Nuclear Information System (INIS)

Nystroem, H.; Bera, P.; Nette, P.

1994-01-01

Since 1968, the International Atomic Energy Agency (IAEA) has operated a postal dose intercomparison service based on TLDs. This service has been giving dosimetric support to hospitals with 60 Co teletherapy units in developing countries. The increasing number of medical accelerators installed in developing countries prompted the IAEA to expand the service also to cover high energy X ray beams. For this purpose the energy dependence of the TLDs and a suitable correction procedure for their use were studied. This paper is a discussion of that study. 10 refs, 6 figs, 2 tabs

Model Regulations for the Use of Radiation Sources and for the Management of the Associated Radioactive Waste. Supplement to IAEA Safety Standards Series No. GS-G-1.5

International Nuclear Information System (INIS)

2015-01-01

IAEA Safety Standards Series No. GSR Part 1, Governmental, Legal and Regulatory Framework for Safety, requires that governments establish laws and statutes to make provisions for an effective governmental, legal and regulatory framework for safety. The framework for safety includes the establishment of a regulatory body. The regulatory body has the authority and responsibility for promulgating regulations, and for preparing their implementation. This publication provides advice on an appropriate set of regulations covering all aspects of the use of radiation sources and the safe management of the associated radioactive waste. The regulations provide the framework for the regulatory requirements and conditions to be incorporated into individual authorizations for the use of radiation sources in industry, medical facilities, research and education and agriculture. The regulations also establish criteria to be used for assessing compliance. This publication allows States to appraise the adequacy of their existing regulations and regulatory guides, and can be used as a reference for those States developing regulations for the first time. The regulations set out in this publication will need to be adapted to take account of local conditions, technical resources and the scale of facilities and activities in the State. The set of regulations in this publication is based on the requirements established in the IAEA safety standards series, in particular in IAEA Safety Standards Series No. GSR Part 3 (Interim), Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, in IAEA Safety Standards Series No. GSR Part 5, Predisposal Management of Radioactive Waste, and in IAEA Safety Standards Series No. SSR-5, Disposal of Radioactive Waste. They are also derived from the Code of Conduct of the Safety and Security of Radiation Sources and the Guidance on the Import and Export of Radioactive Sources. This publication allows States to appraise the

Model Regulations for the Use of Radiation Sources and for the Management of the Associated Radioactive Waste. Supplement to IAEA Safety Standards Series No. GS-G-1.5

International Nuclear Information System (INIS)

2013-12-01

IAEA Safety Standards Series No. GSR Part 1, Governmental, Legal and Regulatory Framework for Safety, requires that governments establish laws and statutes to make provisions for an effective governmental, legal and regulatory framework for safety. The framework for safety includes the establishment of a regulatory body. The regulatory body has the authority and responsibility for promulgating regulations, and for preparing their implementation. This publication provides advice on an appropriate set of regulations covering all aspects of the use of radiation sources and the safe management of the associated radioactive waste. The regulations provide the framework for the regulatory requirements and conditions to be incorporated into individual authorizations for the use of radiation sources in industry, medical facilities, research and education and agriculture. The regulations also establish criteria to be used for assessing compliance. This publication allows States to appraise the adequacy of their existing regulations and regulatory guides, and can be used as a reference for those States developing regulations for the first time. The regulations set out in this publication will need to be adapted to take account of local conditions, technical resources and the scale of facilities and activities in the State. The set of regulations in this publication is based on the requirements established in the IAEA safety standards series, in particular in IAEA Safety Standards Series No. GSR Part 3 (Interim), Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, in IAEA Safety Standards Series No. GSR Part 5, Predisposal Management of Radioactive Waste, and in IAEA Safety Standards Series No. SSR-5, Disposal of Radioactive Waste. They are also derived from the Code of Conduct of the Safety and Security of Radiation Sources and the Guidance on the Import and Export of Radioactive Sources. This publication allows States to appraise the

Comparative Study on Research Reactor Operation Requirements of IAEA and Korea

International Nuclear Information System (INIS)

Yune, Young Gill; Chang, Woo Joon; Lee, Jinho

2014-01-01

The IAEA safety requirements represent a consensus view of the IAEA's member states and encompass the recommendations of international experts for the safety of the research reactor. The IAEA safety standards are acknowledged as a global standard by most countries in the world. Therefore, it is desirable to harmonize domestic safety requirements with those of the IAEA. Also, since the IAEA safety requirements include international endeavors to strengthen nuclear safety and to apply the latest nuclear safety technologies to nuclear facilities, a comparative analysis of the safety requirements of the IAEA and Korea for the research reactor will be beneficial to obtaining the insights to improve regulations of the research reactor in Korea. For the reason, a comparative study has been conducted for the research reactor operation safety requirements of the IAEA and Korea in this paper. This paper briefly introduced operation safety requirements in the NS-R-4, analysis methods of this study, and the analysis results. A comparative study has been performed on research reactor operation safety requirements of the IAEA and Korea. This study has identified some gaps in operation safety requirements for the NPP of Korea, comparing with those for the research reactor of the IAEA in the following areas: periodic safety assessment, utilization and modification of the reactor, extended shutdown, inspection/testing/maintenance, operating organization, emergency planning, and commissioning

Quality assurance for IAEA inspection planning

International Nuclear Information System (INIS)

Markin, J.T.

1986-01-01

Under the provisions of the Treaty on Nonproliferation of Nuclear Weapons and other agreements with states, the International Atomic Energy Agency (IAEA) conducts inspections at nuclear facilities to confirm that their operation is consistent with the peaceful use of nuclear material. The Department of Safeguards at the IAEA is considering a quality assurance program for activities related to the planning of these facility inspections. In this report, we summarize recent work in writing standards for planning inspections at the types of facilities inspected by the IAEA. The standards specify the sequence of steps in planning inspections, which are: (1) administrative functions, such as arrangements for visas and travel, and communications with the state to confirm facility operating schedules and the state's acceptance of the assigned inspectors; (2) technical functions including a specification of the required inspection activities, determination of personnel and equipment resources, and a schedule for implementing the inspection activities at the facility; and (3) management functions, such as pre- and post-inspection briefings, where the planned and implemented inspection activities are reviewed

Performance evaluation of working standard NE2581 in comparison with reference standard NE2561 in the determination of absorbed dose to water using IAEA, HPA, NACP, AAPM, NCRP and ICRU protocols

International Nuclear Information System (INIS)

Dolah, M.T.; Supian Samat; Taiman Kadni

2001-01-01

The aim of this study was to evaluate the performance of NE 2581 in comparison with NE 2561 in the determination of the absorbed dose to water in a γ-ray beam using IAEA, HPA, NACP, AAPM, NCRP and ICRU protocols. 13 exposures of the γ-ray beams were used. This number of exposures yielded 26 chamber rate readings for NE 2581 (N=13) and for NE 2561 (N=13). From the 13 NE 2581 readings, 78 absorbed dose to water values were calculated for the IAEA (N=13), HPA (N=13), NACP (N=13), AAPM (N=13), NCRP (N=13) and ICRU (N=13) protocols. Similarly, from the 13 NE 2561 readings, 78 absorbed dose to water values were calculated for IAEA (N=13), HPA (N=13), NACP (N=13), AAPM (N=13), NCRP (N=13) and ICRU (N=13) protocols. From these 156 (=78 x 2) absorbed dose to water values, 78 percentage deviations between the NE 2581 and NE 2561 results were calculated for IAEA (N=13), HPA (N=13), NACP (N=13), AAPM (N=13), NCRP (N=13) and ICRU (N=13) protocols. For a single protocol, the mean μ and standard error σ+s+e of the percentage deviations (N=13) were calculated. results obtained in terms of [protocol, μ ± σ se ] were [IAEA,1.55 ± 0.12], [HPA, 0.98 ± 0.12], [NACP, 1.93 ± 0.12], [AAPM, -0.06 ± 0.12], [NCRP, 0.97 ± 0.12], [ICRU, 0.97 ± 0.12]. It can be seen that the range of percentage deviations is from -0.06 to 1.93. As the quoted IAEA acceptable limit of deviation is ± 3.0%, it was concluded that the working standard NE 2581 chamber has shown acceptable performance. In addition, the use of the AAPM protocol has enable NE 2581 to show a performance that is very similar like NE 2561. (Author)

Comparative Study on Research Reactor Design Requirements between IAEA and Korea

International Nuclear Information System (INIS)

Chang, Won Joon; Yune, Young Gill; Song, Myung Ho; Cho, Seung Ho

2013-01-01

This study has identified the gaps in the safety requirements for design of research reactors of Korea comparing with those of the IAEA. The review results showed that the gaps have arisen mainly from the following aspects: - The differences in the characteristics of design and operation between power reactor and research reactor - Enhancement of the level of safety of nuclear reactor facility - Consideration of advanced safety technologies. The review results will be utilized to reflect the IAEA safety requirements for design of research reactors into those of Korea, which will contribute to enhancing the level of safety and improving the technical standards of research reactors of Korea. The IAEA safety standards encompass international consensus to strengthen the nuclear safety and to reflect the latest advancement of nuclear safety technologies. Also, they provide reliable means to ensure the effective fulfillment of obligations under the various international safety conventions. Many countries have adopted the IAEA safety standards as their national standards in nuclear regulations. Since Korea has exported research reactor technologies abroad these days and will continue to export them in the future, it is desirable to harmonize domestic safety requirements for research reactor with those of the IAEA. The KINS (Korea Institute of Nuclear Safety) has performed a review of the IAEA safety requirements for design of research reactors comparing with those of Korea. The purpose of this comparative study is to harmonize the safety requirements for the design of research reactors of Korea with those of the IAEA as a member state of the IAEA, and to encompass global efforts to enhance the nuclear safety and to reflect the latest advancement of nuclear safety technologies into the safety requirements for the design of research reactors of Korea. Design requirements for structures, systems, and components of research reactors important to safety, which are required to

Guidance for the application of the leak before break concept. Report of the IAEA extrabudgetary programme on the safety of WWER-440 model 230 nuclear power plants

International Nuclear Information System (INIS)

1994-11-01

This document provides additional guidance on application of the LBB concept to WWER-440/230 NPPs and complements the IAEA-TECDOC-710. The objective of the report is to describe in detail the elements of the LBB concept, the necessary support as well as the condition to be fulfilled, and the verification programme. It should also provide a clear picture of all the activities and resources needed to implement the LBB successfully as a comprehensive concept

IAEA data base system for nuclear research reactors (RRDB)

International Nuclear Information System (INIS)

Lipscher, P.

1986-01-01

The IAEA Data Base System for Nuclear Research Reactors (RRDB) User's Guide is intended for the user who wishes to understand the concepts and operation of the RRDB system. The RRDB is a computerized system recording administrative, operational and technical data on all the nuclear research reactors currently operating, under construction, planned or shut down in IAEA Member States. The data is received by the IAEA from reactor centres on magnetic tapes or as responses to questionnaires. All the data on research, training, test and radioactive isotope production reactors and critical assemblies is stored on the RRDB system. A full set of RRDB programs (in NATURAL) are contained at the back of this Guide

Comparison of Kayzero for Windows and k0-IAEA software packages for k0 standardization in neutron activation analysis

Czech Academy of Sciences Publication Activity Database

Kubešová, Marie; Kučera, Jan

2011-01-01

Roč. 654, č. 1 (2011), s. 206-212 ISSN 0168-9002 R&D Projects: GA ČR GA202/09/0363 Institutional research plan: CEZ:AV0Z10480505 Keywords : neutron activation analysis * ko standardization * Kayzero for Windows program * ko-IAEA program Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 1.207, year: 2011

IAEA yearbook 1991

International Nuclear Information System (INIS)

1991-01-01

The IAEA Yearbook 1991 contains the following 6 chapters: Transfer of Nuclear Technology; Applications of Nuclear Techniques and Research (Also published separately as Part B of the IAEA Yearbook 1991); Nuclear Power, Nuclear Fuel Cycle and Waste Management (Also published separately as Part C of the IAEA Yearbook 1991); Nuclear Safety Review (Also published separately as Part D of the IAEA Yearbook 1991); IAEA Safeguards; The IAEA (operating framework and functions). A separate abstract and indexing was provided for each chapter. Refs, figs and tabs

Radiation protection glossary. Selected basic terms used in IAEA publications

Energy Technology Data Exchange (ETDEWEB)

1986-01-01

The glossary is intended to be used as a terminology standard for IAEA documentation on radiation protection. An effort has been made to use definitions contained in internationally accepted publications such as recommendations of the International Commission on Radiological Protection (ICRP), standards of the International Organization for Standardization (ISO) and of the International Electrotechnical Commission (IEC), reports of the International Commission on Radiation Units and Measurements (ICRU), with only slight modifications in order to tailor them more closely to IAEA needs. The glossary is restricted to ionizing radiation.

IAEA safeguards

International Nuclear Information System (INIS)

1985-01-01

IAEA safeguards are a system of technical measures within the framework of international non-proliferation policy entrusted to the IAEA in its Statute and by other treaties. About 98% of the world's nuclear installations outside the nuclear-weapon countries are now under safeguards. This paper gives a review of IAEA activities in this field: objectives, agreements, work and development of staff of the IAEA's Department of Safeguards, instruments and techniques for direct measurement and verification of nuclear material. (author)

17. IAEA fusion energy conference. Extended synopses

International Nuclear Information System (INIS)

1998-01-01

Book of extended synopses of the papers, accepted by a international programme committee for presentation at the 17th IAEA Fusion Energy Conference in Yokohama, Japan. The subjects covered are magnetic confinement experiments, plasma heating and current drive, ITER EDA, inertial fusion energy, innovative concepts, fusion technology and theory

NIRS inaugurated as IAEA Collaborating Centre. Its presence and function

International Nuclear Information System (INIS)

Yonekura, Yoshiharu; Watanabe, Naoyuki; Sakai, Kazuo; Kamada, Tadashi; Imai, Reiko; Fujibayashi, Yasuhisa; Nakane, Takeshi; Burkart, W.; Chhem, R.; Matsuura, Shojiro

2010-01-01

The feature article is the collection of documents commemorating the 2010 designation of National Institute of Radiological Sciences (NIRS) as one of International Atomic Energy Agency (IAEA) Collaborating Centres (CC) again, involving 4 introductory chapters containing 9 sections in total. The IAEA-CC concept, essentially for the 4-year project, started to globally give shape by designating 3 organizations in some countries in 2004, NIRS as a CC worked from 2006 and the present designation is the renewed one. There are 17 IAEA-CCs at present. The title of Chapter 1 of the article is the same as above title by NIRS President and of Chapter 2, ''IAEA-CC scheme'' by NIRS Senior Specialist/ professor of Gunma Pref. College of Health Sciences/ former IAEA staff. Chapter 3 entitled ''Research Development of Next Four Years in Three Collaboration Areas'', contains 3 topics of the very areas mainly responsible to the project, of biological effect and mechanism of low dose radiation by NIRS Director of Res. Center for Radiation Protection, IAEA-CC plan (radiotherapy) by the Director for Charged Particle Therapy, and IAEA-CC activity and research at Molecular Imaging Center by its Director. Chapter 4 entitled ''Expectation to NIRS'' contains four topics; Expectations for the reinforcement of collaboration with IAEA whose new priority is cancer control by the Japanese Ambassador Extraordinary and Plenipotentiary in Vienna; Welcoming NIRS to join IAEA-CC network (an interview with IAEA Deputy Director General and Head of Nuclear Sciences and Applications); Honoured to invite NIRS to establish a new partnership with IAEA (an interview with IAEA Director of Division of Human Health, Dept. of Nuclear Sciences and Applications); Expectation to NIRS in peaceful use of nuclear and radiation by President of the Nuclear Safety Research Association. (T.T.)

Establishing the standard X-ray beam qualities for calibration of dosimeters used in diagnostic radiology following IAEA-TRS457

International Nuclear Information System (INIS)

Duong Van Trieu; Ho Quang Tuan; Bui Duc Ky

2014-01-01

The determination of the patient dose needs to provide a reference dose for the patient that reference dose levels to assess the relative risk during X- ray diagnostic. This mission, We had established a number of standard beam qualities to perform calibrations of diagnostic dosimeters and methods of measuring patient dose in X-ray diagnostic. At radiation dosimetry room, we had establish RQR2, RQR3, RQR4, RQR5, RQR6 beam qualities based on IAEA-TRS457 documentation with homogeneity coefficient (h) for each beam quality in the range 0.7 - 0.8, and haft-value layers HVL1, HVL2 of experimental and IAEA is different about 10%. Established calibration method for diagnostic dosimeters as KAP meters, UNFORS dosimeters, and the TLD dosimeters, practical measurements of entrance surface air kerma on Shimadzu X-ray machines used phantom. (author)

Appraisal for Japan of the safety of transport of radioactive material. Provision for the application of the IAEA safety standards

International Nuclear Information System (INIS)

2006-01-01

The IAEA's Statute authorizes it to provide for the application of its standards at the request of any State. The objective of a TranSAS appraisal is to assist any requesting State to achieve a high level of safety in the transport of radioactive material by reviewing its implementation of the Transport Regulations and by making recommendations for improvement where appropriate.The IAEA discharges this statutory function through a number of mechanisms, including rendering independent peer review appraisal services to determine the status of compliance with its standards. The appraisal for Japan in December 2005 on the safety of the transport of radioactive material is the seventh TranSAS mission since the inception of the service. This report presents its findings. The TranSAS appraisal team completed a comprehensive appraisal of the implementation of the Transport Regulations in Japan. The cooperation of the authorities in Japan, and of all those who participated in the discussions, was excellent and contributed to the success of the appraisal. The comprehensive legal framework, with responsibilities identified in considerable detail and with clear lines of authority to minimize overlap of responsibilities, provides a sound basis for the implementation of the Transport Regulations. Generally, the Transport Regulations are implemented in accordance with IAEA requirements. Some areas for possible improvement have been identified. These areas relate mainly to reduction of regulations, quality management systems, training, compliance assurance and lessening the administrative burden for incorporating amendments to the IMDG Code. The findings include a considerable number of good practices, in particular in the area of maritime transport

17. IAEA fusion energy conference. Extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-31

Book of extended synopses of the papers, accepted by a international programme committee for presentation at the 17th IAEA Fusion Energy Conference in Yokohama, Japan. The subjects covered are magnetic confinement experiments, plasma heating and current drive, ITER EDA, inertial fusion energy, innovative concepts, fusion technology and theory Refs, figs, tabs

Review of the Commission program for standardization of nuclear power plants and recommendations to improve standardization concepts

International Nuclear Information System (INIS)

1978-02-01

This is a report of a staff study describing the need and utility of specific changes to the Commission's standardization program. The various matters considered in the study include: (1) A discussion of industry use to date of the standardization program. (2) A discussion of the experience to date with each of the standardization concepts. (3) A review of public comments on the standardization program and the staff response to each principal comment. (4) A review of the need for standardization considering the likely number of license applications to be submitted in the coming years. (5) A discussion of the reference system concept, including review of applicable experience and recommended changes to the concept. (6) A discussion of the duplicate plant concept, including review of applicable experience and recommended changes to the concept. (7) A discussion of the manufacturing license concept, including review of applicable experience and recommended changes to the concept. (8) A discussion of the replicate plant concept, including review of applicable experience and recommended changes to the concept. (9) A discussion of the effective periods for approved designs under all four standardization concepts. (10) A description of continuing staff activities related to the standardization program

An introduction to a new IAEA safety guide: 'ageing management for nuclear power plants'

International Nuclear Information System (INIS)

Pachner, J.; Inagaki, T.; Kang, K.S.

2008-01-01

This paper reports on a new IAEA Safety Guide entitled 'Ageing Management for Nuclear Power Plants' which is currently in an advanced draft form, awaiting approval of publication. The new Safety Guide will be an umbrella document for a comprehensive set of guidance documents on ageing management which have been issued by the IAEA. The Safety Guide first presents basic concepts of ageing management as a common basis for the recommendations on: proactive management of ageing throughout the life cycle of a nuclear power plant (NPP); systematic approach to managing ageing in the operation of NPPs; managing obsolescence; and review of ageing management for long term operation (life extension). The Safety Guide is intended to assist operators in establishing, implementing and improving systematic ageing management programs in NPPs and may be used by regulators in preparing regulatory standards and guides, and in verifying that ageing in nuclear power plants is being effectively managed. (author)

The IAEA's Universal Instrument Token

International Nuclear Information System (INIS)

Naumann, I.; Wishard, B.; Morgan, K.; Christoph, B.; Schwier, A.; Frank, T.

2015-01-01

The IAEA currently seeks to improve the harmonization of security approaches across safeguards equipment. The protection of digital safeguards data is based on several principles: a) the signing of data in measurement devices using standard public/private-key-based signature generation, b) the storage of secret keys on certified, tamper-protected cryptographic devices, and c) well-established cryptographic algorithms and protocols based on global standards and internationally recognized cryptographic libraries. This paper discusses a cryptographic token, the Universal Instrument Token, which constitutes the core element of the architecture for signing safeguards data. This architecture supports the above principles and is compliant with the IAEA's information security policies and guidelines. An important side-condition is that the UIT must be implemented across a wide range of operating systems and hardware architectures, which mandates the use of open-source software for all software-related parts involved. The UIT is permanently connected to the measuring device (usually via the USB port) and requires complex hardware drivers and middleware components. Identifying open-source based, mature and ready-for-use smart card drivers and tools that are compatible with a range of operating systems was a major challenge. Reliable and well-established cryptographic libraries reside at the core of every information-security application. Different types of review software, typically software products used at IAEA headquarters in Vienna but occasionally also in the facilities, need to contain some specific software modules in order to verify the digital signatures attached to the data. Finally, also required are enrollment tools which generate private keys and certify their corresponding public counterparts using the IAEA's internal Certification Authority. In 2014, the roll-out of the UIT has raised the security of IAEA instrument data signing to a level which is

Current status of ground motions evaluation in seismic design guide for nuclear power facilities. Investigation on IAEA and US.NRC

International Nuclear Information System (INIS)

Nakajima, Masato; Ito, Hiroshi; Hirata, Kazuta

2009-01-01

Recently, IAEA (International Atomic Energy Agency) and US.NRC (US. Nuclear Regulatory Commission) published several standards and technical reports on seismic design and safety evaluation for nuclear power facilities. This report summarizes the current status of the international guidelines on seismic design and safety evaluation for nuclear power facilities in order to explore the future research topics. The main results obtained are as follows: 1 IAEA: (1) In the safety standard series, two levels are defined as seismic design levels, and design earthquake ground motion is determined corresponding to each seismic design level. (2) A new framework on seismic design which consists of conventional deterministic method and risk-based method is discussed in the technical report although the framework is not adopted in the safety guidelines. 2 USA: (1) US.NRC discusses a performance-based seismic design framework which has been originally developed by the private organization (American Society of Civil Engineers). (2) Design earthquakes and earthquake ground motion are mainly evaluated and determined based on probabilistic seismic hazard evaluations. 3 Future works: It should be emphasized that IAEA and US.NRC have investigated the implementation of risk-based concept into seismic design. The implementation of risk-based concept into regulation and seismic design makes it possible to consider various uncertainties and to improve accountability. Therefore, we need to develop the methods for evaluating seismic risk of structures, and to correlate seismic margin and seismic risk quantitatively. Moreover, the probabilistic method of earthquake ground motions, that is required in the risk-based design, should be applied to sites in Japan. (author)

IAEA report on the Fukushima-Daiichi accident and safety standards

International Nuclear Information System (INIS)

Mizumachi, Wataru

2011-01-01

On March 11th, 2011, 4th largest earthquake attacked Fukushima Nuclear Power Plant and around one hour later, the enormous Tsunami attacked it also. After the large earthquake attacked, the automatic shutdown was performed and the emergency diesel generators automatically started and Isolation condenser cooled down the core for unit 1 and RCIC cooled down the cores for unit 2 and 3. However, the large Tsunami damaged all emergency diesel generators and all ECCS pumps. The core melted and the hydrogen gas were generated by the steam and the zircaloy reaction. The hydrogen leaked into the reactor building and then the reactor building blasted by the hydrogen. IAEA has organized the Great East Japan Earthquake Expert Mission on Fukushima-daiichi accident and they reported to the formal meeting in the headquater in Viena. They made 15 conclusions and 16 lessons and learned. IAEA chairman officially summarized 28 recommendations from them. USNRC published 'Recommendations for Enhanuing Reactor Safety in the 21st Century 'where they summarized 12 Recommendations on Fukushima Accident. Here is the summary of these recommendations. (author)

IAEA inspection activities in the model country

International Nuclear Information System (INIS)

Madueme, G.

1989-01-01

An overview of the activities undertaken by IAEA inspectors at the model research reactor and research laboratories is given. The basic philosophy behind nuclear material stratification and the concepts of Material Balance Areas and Key Measurement Points are explained. Diversion routes and plausible diversion scenarios are analysed. 8 refs., 6 figs., 3 tabs., poster presentations included

19. IAEA fusion energy conference. Book of abstracts

International Nuclear Information System (INIS)

2002-01-01

Book of abstracts of the papers, accepted by an international programme committee for presentation at the 19th IAEA Fusion Energy Conference in Lyon, France. The subjects covered are magnetic confinement experiments, plasma heating and current drive, ITER EDA, inertial fusion energy, innovative concepts, fusion technology and theory

The IAEA and Control of Radioactive Sources

International Nuclear Information System (INIS)

Dodd, B.

2004-01-01

The presentation discusses the authoritative functions and the departments of the IAEA, especially the Department of Nuclear Safety and Security and its Safety and Security of Radiation Sources Unit. IAEA safety series and IAEA safety standards series inform about international standards, provide underlying principles, specify obligations and responsibilities and give recommendations to support requirements. Other IAEA relevant publications comprise safety reports, technical documents (TECDOCs), conferences and symposium papers series and accident reports. Impacts of loss of source control is discussed, definitions of orphan sources and vulnerable sources is given. Accidents with orphan sources, radiological accidents statistic (1944-2000) and its consequences are discussed. These incidents lead to development of the IAEA guidance. The IAEA's action plan for the safety of radiation sources and the security of radioactive material was approved by the IAEA Board of Governors and the General Conference in September 1999. This led to the 'Categorization of Radiation Sources' and the 'Code of Conduct on the Safety and Security of Radioactive Sources'. After 0911 the IAEA developed a nuclear security plan of activities including physical protection of nuclear material and nuclear facilities, detection of malicious activities involving nuclear and other radioactive materials, state systems for nuclear material accountancy and control, security of radioactive material other than nuclear material, assessment of safety and security related vulnerability of nuclear facilities, response to malicious acts, or threats thereof, adherence to and implementation of international agreements, guidelines and recommendations and nuclear security co-ordination and information management. The remediation of past problems comprised collection and disposal of known disused sources, securing vulnerable sources and especially high-risk sources (Tripartite initiative), searching for

The IAEA's WorldAtom Internet site: International news and information services

International Nuclear Information System (INIS)

Kyd, D.R.

2000-01-01

The International Atomic Energy Agency (IAEA) provides news and public information services via the Internet through its WorldAtom home page. The page is accessible at www.iaea.org/worldatom. Following are brief highlights of the items available on the site by clicking Press Centre, Reference Centre, or other links: Daily Press Review: Summaries of selected news items pertaining to global nuclear developments and the IAEA's work are provided each day, drawing upon a wide range of global media sources. IAEA NewsBriefs: Regularly featured are updates about IAEA activities related to areas of safety, technology transfer, and nuclear safeguards. Meetings and training courses: News about IAEA-sponsored symposia, seminars, and other meetings, as well as information about international meetings on atomic energy sponsored by other organizations, are updated on a daily basis. Press releases and statements: All IAEA press releases and media advisories since 1995 are accessible on the site. Topical and feature pages: In-depth coverage and links to information resources within and outside the IAEA are regularly given to selected topics of high international interest involving the IAEA. IAEA publications: listings and overviews of IAEA technical reports, safety standards, and other publications are updated as they are issued. Scientific and technical information: WorldAtom includes links (Reference Centre) to the International Nuclear Information System, IAEA's extensive bibliographic database of references and resources, to the nuclear database, and to departmental pages at IAEA that focus on IAEA programs and activities. IAEA documents: Electronic versions of official IAEA documents are added as they are issued. These documents include the texts and status lists of international conventions under IAEA auspices; IAEA information circulars to member states; IAEA annual reports (since 1995); and background reports and documents for the IAEA General Conference related to

Study of essential safety features of a three-loop 1,000 MWe light water reactor (PWR) and a corresponding heavy water reactor (HWR) on the basis of the IAEA nuclear safety standards

International Nuclear Information System (INIS)

1989-02-01

Based on the IAEA Standards, essential safety aspects of a three-loop pressurized water reactor (1,000 MWe) and a corresponding heavy water reactor were studied by the TUeV Baden e.V. in cooperation with the Gabinete de Proteccao e Seguranca Nuclear, a department of the Ministry which is responsible for Nuclear power plants in Portugal. As the fundamental principles of this study the design data for the light water reactor and the heavy water reactor provided in the safety analysis reports (KWU-SSAR for the 1,000 MWe PWR, KWU-PSAR Nuclear Power Plant ATUCHA II) are used. The assessment of the two different reactor types based on the IAEA Nuclear Safety Standards shows that the reactor plants designed according to the data given in the safety analysis reports of the plant manufacturer meet the design requirements laid down in the pertinent IAEA Standards. (orig.) [de

Scientific committee of the IAEA/WHO Network of Secondary Standard Dosimetry Laboratories. Report of the ninth meeting of the SSDL scientific committee, IAEA, Vienna, 13-17 November 2000

International Nuclear Information System (INIS)

2001-01-01

The report of the eighth meeting (held in Oct. 1998) of the Scientific Committee (SSC) of the IAEA/WHO network of Secondary Standard Dosimetry Laboratories (SSDL) was published in the SSDL Newsletter No. 40, January 1999. The ninth meeting was held in Vienna at Agency Headquarters from 13 to 17 November 2000. Opening remarks were made by Mr. S. Groth, Director, Division of Human Health (NAHU), Mr. H. Oestensen (WHO), Co-Secretary of the IAEA/WHO SSDL Network, and Mr. Ahmed Meghzifene, acting Section Head, Dosimetry and Medical Radiation Physics (DMRP). The Agency's DMRP sub-programme provides traceable radiation standards to the majority of developing countries over a wide range of energies and dose levels. External-beam radiation therapy and radiation processing (high dose) have a long history and robust links to international standards. Recently the DMRP has developed projects providing robust links for calibration of mammography X-ray beams, brachytherapy sources, and personnel monitoring programmes at the participating SSDLs. Efforts by the Agency and the WHO over the past 5 years have made significant improvements in the return rate and turn-around time in the postal TLD programme, effectively increasing the availability of Agency standards. Two other high-priority items promulgated by the DMRP are: (i) follow-up of quality audit measurements which fall outside the established action levels, and (ii) transfer of postal TLD programmes to national programmes and establishing and maintaining links between these programmes and the DMRP. The SSC still considers both of these as high priority items, commends the DMRP on their efforts, and encourages them to continue to develop activities in these areas. The SSC wishes to emphasize that radiation dosimetry is a necessary adjunct to many programmes that utilize ionizing radiation at various dose levels. The SSC commends the Agency for their continued support for the programmes sponsored through the Dosimetry and

Japanese contributions to IAEA INTOR workshop, phase IIA

International Nuclear Information System (INIS)

Fujisawa, Noboru; Sugihara, Masayoshi; Shimada, Michiya; Saito, Seiji.

1982-11-01

This report corresponds to Chapter VI of Japanese contribution report to IAEA INTOR workshop, Phase IIA. Special emphasis is placed on pumped limiter analysis for comparative studies between limiter and divertor concepts. Pumping characteristics of divertor/limiter and radiation cooling of diverted plasmas by impurities are also intensively studied. (author)

The radiation safety standards programme

International Nuclear Information System (INIS)

Bilbao, A.A.

2000-01-01

In this lecture the development of radiation safety standards by the IAEA which is a statutory function of the IAEA is presented. The latest editions of the basic safety standards published by the IAEA in cooperation with ICRP, FAO, ILO, NEA/OECD, PAHO and WHO are reviewed

IAEA safeguard system

International Nuclear Information System (INIS)

Pontes, B.C.

1987-01-01

The intents of IAEA safeguards, analysing into the IAEA statutes, are presented. The different types of safeguard agreements; the measurements of accounting, containment and caution used by the operator and; the information to be provided and the verification to be developed by IAEA are described. (M.C.K.) [pt

Statement on Iran by the IAEA Spokesperson

International Nuclear Information System (INIS)

2018-01-01

Full text: In December 2015, IAEA Director General Yukiya Amano presented the Final Assessment on past and present outstanding issues regarding Iran’s nuclear programme to the IAEA Board of Governors. In the report, the Agency assessed that, before the end of 2003, an organizational structure was in place in Iran suitable for the coordination of a range of activities relevant to the development of a nuclear explosive device. Although some activities took place after 2003, they were not part of a coordinated effort. The Agency’s overall assessment was that a range of activities relevant to the development of a nuclear explosive device were conducted in Iran prior to the end of 2003 as a coordinated effort, and some activities took place after 2003. The Agency also assessed that these activities did not advance beyond feasibility and scientific studies, and the acquisition of certain relevant technical competences and capabilities. The same report stated that the Agency had no credible indications of activities in Iran relevant to the development of a nuclear explosive device after 2009. Based on the Director General’s report, the Board of Governors declared that its consideration of this issue was closed. In line with standard IAEA practice, the IAEA evaluates all safeguards-relevant information available to it. However, it is not the practice of the IAEA to publicly discuss issues related to any such information. (author)

Establishment of external quality assurance procedures with FAO/IAEA ELISA kits. Report of an FAO/IAEA consultants meeting

International Nuclear Information System (INIS)

1994-01-01

As part of the programme of support to scientists in developing countries, the Joint FAO/IAEA Division has developed and distributed ELISA kits for detecting both the causative agent and the immune response of animals to a number of the major diseases affecting livestock. In many cases these kits are now being used as part of national and international control and/or eradication programmes (e.g. for rinderpest, trypanosomosis, foot and mouth disease, brucellosis) and are likely to form the basis for establishing a country's freedom from particular diseases (e.g. rinderpest) at the national and international level. To further encourage international trade in livestock and livestock products, and to assist in the regional or global control and eradication of a number of the major diseases affecting livestock, there has been a strong move towards international standardization for animal disease diagnosis. Central to this is the need for internal and external quality assurance procedures to ensure that a standardized approach is being adhered to and that the results can be relied upon. In 1992, an FAO/IAEA consultants meeting was convened to define and establish for the ELISA, standards for internal quality control of reagents and procedures and for the expression of results. The recommendations of that meeting have now been incorporated in all FAO/IAEA ELISA kits and have been adopted by the OIE (Office International des Epizooties). The primary function of the internal quality controls is to ensure that the assay is performing within defined limits. Equally important, is an assurance to all outside interested bodies (national veterinary authorities, international organizations, donor organizations, trading partners) that the results being provided by a laboratory are valid. The procedures for ascertaining this assurance would form the basis of an external quality assurance programme (EQAP). Between 1990 and 1993, as part of establishing an EQAP, laboratories using

The IAEA/WHO Network of SSDLs. Short history, activity and future trends

International Nuclear Information System (INIS)

Svensson, Hans; Zsdanszky, Kalman

1990-01-01

In 1968 at an IAEA meeting in Caracas, Venezuela, the dosimetric requirements of radiotherapy centres were discussed. At that time many radiotherapy departments in developing countries did not have a dosimeter. Even those that had a dosimeter were seldom able to send it to a Primary Standard Dosimetry Laboratory (PSDL) for proper calibration. The establishment of regional dosimeter calibration laboratories was recommended by the participating experts including representatives of WHO. There was general consent that it was not necessary to establish in every country a PSDL, which would need a very qualified staff and sophisticated equipment. Instead, the establishment of Secondary Standard Dosimetry Laboratories (SSDLs) was found to be an adequate solution to the problem. The new idea of SSDLs and their role within the international metrology system was thoroughly discussed at a joint IAEA/WHO meeting in Rio de Janeiro (scientific secretaries: H.H. Eisenlohr, IAEA and W. Seelentag, WHO) in December 1974. Considering the fact that an SSDL cannot work in isolation the experts recommended the setting up of an international Network of SSDLs under the auspices of the IAEA and WHO. The statutes of the IAEA/WHO Network of SSDLs were laid down in a Working Arrangement between the IAEA and WHO in April 1976. Later in 1976 the two Directors General of the IAEA and WHO formally announced by circular letters to their respective member states the establishment of the IAEA/WHO Network of SSDL. The Criteria for the Establishment of a Secondary Standard Dosimetry Laboratory were formulated by an Advisory Group and were attached to these letters. At that time there existed already 8 laboratories, which had been designated by WHO during the period 1968-1976 as regional reference centres for dosimetry. Another SSDL had been set up in Rio de Janeiro in collaboration between the Brazilian Government, the Government of the Federal Republic of Germany, and the IAEA. As a consequence of the

Role IAEA implementation of ICRP-60 on regulations the safe transport of radioactive material

International Nuclear Information System (INIS)

Elshinawy, R.K.M.; Gomaa, M.A.

1994-01-01

In november 1990, the (ICRP) adopted its 1990 recommendations (ICRP-60) ( 1). These recommendations will significantly influence not only IAEA's basic safety standards (safety series 9) ( 2), but also the IAEA regulations for the safe transport of radioactive material ( 3) and its supporting documents ( 4-6). IAEA experts are currently engaged in the revision of the transport regulations. This revision process led to the publication of the revised transport regulations of 1966. The transport regulations are developed to ensure safety during movement of radioactive materials, and to provide reasonable assurance that the transport activities comply with the basic safety standards for radiation protection

Stability of reference class ionization chambers used for radiotherapy dosimetry: IAEA experience

International Nuclear Information System (INIS)

Czap, L.; Meghzifene, A.; Shortt, K.R.; Andreo, P.

2002-01-01

The IAEA calibrates ionization chambers, used in radiotherapy, for its Member States. The calibrations are either for Secondary Standards Dosimetry Laboratories (SSDLs) or hospitals from countries without a SSDL. For that purpose, the IAEA calibrates mainly reference class instruments that are in turn used to cross-calibrate field class instruments at the hospital. Typically, the IAEA calibrates about 30-40 ionization chambers per year, of which about half are new chambers purchased by the IAEA for its Member States using Technical Cooperation funds. The IAEA database includes the calibration coefficients of 189 reference class ionization chambers of the following types: NE-2561/2611, NE-2571, W-30001/W-30010. The results of the calibrations and recalibrations of the ionization chambers in terms of air kerma and absorbed dose to water are presented and discussed. The ratio of 60 Co calibration coefficients N D,w /N K , labelled C K , was determined for all chambers. The use of C K as a chamber dependent parameter and quality control indicator to check the results of the routine IAEA calibrations is discussed. In the process of its routine calibrations, the IAEA identified a specific problem related to the W- 30001 ionization chambers. The stability of these chambers was found to exceed the 0.5% tolerance limit set by the International IEC standard. Other SSDLs reported similar findings. The manufacturer stopped the production of these W-30001 chambers to investigate the reasons for this anomalous behaviour. After identifying and correcting the problem, the manufacturer produced a new type of ionization chamber. Five of these chambers were tested at the IAEA and found to be within the tolerance limit

International Nuclear Officials Discuss IAEA Peer Reviews of Nuclear Safety Regulations

International Nuclear Information System (INIS)

2011-01-01

Full text: Senior nuclear regulators today concluded a Workshop on the Lessons Learned from the IAEA Integrated Regulatory Review Service (IRRS) Missions. The U.S. Nuclear Regulatory Commission (NRC) hosted the workshop, in cooperation with the International Atomic Energy Agency, in Washington, DC, from 26 to 28 October 2011. About 60 senior regulators from 22 IAEA Member States took part in this workshop. The IRRS programme is an international peer review service offered by the IAEA to its Member States to provide an objective evaluation of their nuclear safety regulatory framework. The review is based on the internationally recognized IAEA Safety Standards. ''The United States Nuclear Regulatory Commission was pleased to host the IAEA's IRRS meeting this week. The discussions over the past three days have provided an important opportunity for regulators from many countries to come together to strengthen the international peer review process,'' said U.S. NRC Chairman Gregory B. Jaczko. ''Especially after the Fukushima Daiichi accident, the global community recognizes that IRRS missions fill a vital role in strengthening nuclear safety and security programs around the world, and we are proud to be a part of this important effort.'' The IAEA Action Plan on Nuclear Safety includes actions focused towards strengthening the existing IAEA peer reviews, incorporating lessons learned and improving their effectiveness. The workshop provided a platform for the exchange of information, experience and lessons learned from the IRRS missions, as well as expectations for the IRRS programme for the near future. Further improvements in the planning and implementation of the IRRS missions in the longer term were discussed. A strong commitment of all relevant national authorities to the IRRS programme was identified as a key element of an effective regulatory framework. The conclusions of the workshop will be issued in November 2011 and the main results will be reported to the IAEA

Optimizing IAEA Safeguards

International Nuclear Information System (INIS)

Varjoranta, Tero

2016-01-01

IAEA safeguards make a vital contribution to international security. Through safeguards, the IAEA deters the spread of nuclear weapons and provides credible assurance that States are honouring their international obligations to use nuclear material only for peaceful purposes. Its independent verification work allows the IAEA to facilitate building international confidence and strengthening collective security for all.

CNEN, IAEA and ISO normative requirements for measurement management

International Nuclear Information System (INIS)

Kibrit, Eduardo

2009-01-01

International standard ISO 10012:2003 establishes requirements for measurement management systems, including requirements for measurement processes and measuring equipment. ISO 9001:2008 presents requirements for quality management systems, including requirements for the control of monitoring and measuring equipment. ISO 17025:2005 presents general requirements for the competence of testing and calibration laboratories. In the nuclear field the requirements for measurement management are established by standards published by the International Atomic Energy Agency (IAEA), and in Brazil, by the National Nuclear Energy Commission (CNEN). The present paper presents and discusses the normative requirements for measurement management, considering requirements established by National Nuclear Energy Commission (CNEN), International Atomic Energy Agency (IAEA), and International Organisation for Standardisation (ISO). (author)

IAEA symposium on international safeguards

International Nuclear Information System (INIS)

1999-01-01

The eighth IAEA Symposium on International Safeguards was organized by the IAEA in cooperation with the Institute of Nuclear Materials Management and the European Safeguards Research and Development Association. It was attended by over 350 specialists and policy makers in the field of nuclear safeguards and verification from more than 50 countries and organizations. The purpose of the Symposium was to foster a broad exchange of information on concepts and technologies related to important developments in the areas of international safeguards and security. For the first time in the history of the symposia, the IAEA is issuing proceedings free of charge to participants on CD-ROM. The twenty-two plenary, technical, and poster sessions featured topics related to technological and policy aspects from national, regional and global perspectives. The theme of the Symposium: Four Decades of Development - Safeguarding into the New Millennium set the stage for the commemoration of a number of significant events in the annals of safeguards. 1997 marked the Fortieth Anniversary of the IAEA, the Thirtieth Anniversary of the Tlatelolco Treaty, and the Twentieth Anniversary of the Department of Safeguards Member State Support Programmes. There were special events and noted presentations featuring these anniversaries and giving the participants an informative retrospective view of safeguards development over the past four decades. The proceedings of this symposium provide the international community with a comprehensive view of where nuclear safeguards and verification stood in 1997 in terms of the growing demands and expectations. The Symposium offered thoughtful perspectives on where safeguards are headed within the broader context of verification issues. As the world of international nuclear verification looks towards the next millennium, the implementation of the expanding and strengthened safeguards system presents formidable challenges

The IAEA/WHO TLD postal programme for radiotherapy hospitals

International Nuclear Information System (INIS)

Izewska, J.; Andreo, P.

2000-01-01

Since 1969 the International Atomic Energy Agency (IAEA), together with the World Health Organization (WHO), has performed postal TLD audits to verify the calibration of radiotherapy beams in developing countries. A number of changes have recently been implemented to improve the efficiency of the IAEA/WHO TLD programme. The IAEA has increased the number of participants and reduced significantly the total turn-around time to provide results to the hospitals within the shortest possible time following the TLD irradiations. The IAEA has established a regular follow-up programme for hospitals with results outside acceptance limits of ±5%. The IAEA has, over 30 years, verified the calibration of more than 3300 clinical photon beams at approximately 1000 radiotherapy hospitals. Only 65% of those hospitals who receive TLDs for the first time have results within the acceptance limits, while more than 80% of the users that have benefited from a previous TLD audit are successful. The experience of the IAEA in TLD audits has been transferred to the national level. The IAEA offers a standardized TLD methodology, provides Guidelines and gives technical back-up to the national TLD networks. The unsatisfactory status of the dosimetry for radiotherapy, as noted in the past, is gradually improving however, the dosimetry practices in many hospitals in developing countries need to be revised in order to reach adequate conformity to hospitals that perform modern radiotherapy in Europe, USA and Australia. (author)

Compliance assessment of an uranium hexafluoride package 30B with overpack to the IAEA standards

International Nuclear Information System (INIS)

Andreuccetti, P.; Aquaro, D.; Forasassi, G.; Beone, G.; Eletti, G.; Orsini, A.

1988-01-01

At the Dipartimento di Costruzioni Meccaniche e Nucleari (DCMN) of the Pisa University a research program was carried out in order to assess the compliance to the updated IAEA standards of the UF6 30B container, complete with its sandwich phenolic foam filled external overpack. The research program, performed in collaboration with ENEA and several interested Italian firms, included 9 mt free drop, perforation, thermal and leaktightness tests, on two complete packages with dummy load. The heat transfer conditions, with the UF6 real contents, were simulated by means of numerical analyses with the TRUMP computer code and calculation procedures set up using the available experimental data. The attained results seem to be useful from the point of view of the foreseen purposes

Verification of a Fissile Material Cut-off Treaty (FMCT): The Potential Role of the IAEA

International Nuclear Information System (INIS)

Chung, Jin Ho

2016-01-01

The objective of a future verification of a FMCT(Fissile Material Cut-off Treaty) is to deter and detect non-compliance with treaty obligations in a timely and non-discriminatory manner with regard to banning the production of fissile material for nuclear weapons or other nuclear devices. Since the International Atomic Energy Agency (IAEA) has already established the IAEA safeguards as a verification system mainly for Non -Nuclear Weapon States (NNWSs), it is expected that the IAEA's experience and expertise in this field will make a significant contribution to setting up a future treaty's verification regime. This paper is designed to explore the potential role of the IAEA in verifying the future treaty by analyzing verification abilities of the Agency in terms of treaty verification and expected challenges. Furthermore, the concept of multilateral verification that could be facilitated by the IAEA will be examined as a measure of providing a credible assurance of compliance with a future treaty. In this circumstance, it is necessary for the IAEA to be prepared for playing a leading role in FMCT verifications as a form of multilateral verification by taking advantage of its existing verification concepts, methods, and tools. Also, several challenges that the Agency faces today need to be overcome, including dealing with sensitive and proliferative information, attribution of fissile materials, lack of verification experience in military fuel cycle facilities, and different attitude and culture towards verification between NWSs and NNWSs

Verification of a Fissile Material Cut-off Treaty (FMCT): The Potential Role of the IAEA

Energy Technology Data Exchange (ETDEWEB)

Chung, Jin Ho [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

The objective of a future verification of a FMCT(Fissile Material Cut-off Treaty) is to deter and detect non-compliance with treaty obligations in a timely and non-discriminatory manner with regard to banning the production of fissile material for nuclear weapons or other nuclear devices. Since the International Atomic Energy Agency (IAEA) has already established the IAEA safeguards as a verification system mainly for Non -Nuclear Weapon States (NNWSs), it is expected that the IAEA's experience and expertise in this field will make a significant contribution to setting up a future treaty's verification regime. This paper is designed to explore the potential role of the IAEA in verifying the future treaty by analyzing verification abilities of the Agency in terms of treaty verification and expected challenges. Furthermore, the concept of multilateral verification that could be facilitated by the IAEA will be examined as a measure of providing a credible assurance of compliance with a future treaty. In this circumstance, it is necessary for the IAEA to be prepared for playing a leading role in FMCT verifications as a form of multilateral verification by taking advantage of its existing verification concepts, methods, and tools. Also, several challenges that the Agency faces today need to be overcome, including dealing with sensitive and proliferative information, attribution of fissile materials, lack of verification experience in military fuel cycle facilities, and different attitude and culture towards verification between NWSs and NNWSs.

IAEA establishes International Seismic Safety Centre

International Nuclear Information System (INIS)

2008-01-01

Full text: The IAEA today officially inaugurated an international centre to coordinate efforts for protecting nuclear installations against the effects of earthquakes. The International Seismic Safety Centre (ISSC), which has been established within the IAEA's Department of Nuclear Safety and Security, will serve as a focal point on seismic safety for nuclear installations worldwide. ISSC will assist countries on the assessment of seismic hazards of nuclear facilities to mitigate the consequences of strong earthquakes. 'With safety as our first priority, it is vital that we pool all expert knowledge available worldwide to assist nuclear operators and regulators to be well prepared for coping with major seismic events,' said Antonio Godoy, Acting Head of the IAEA's Engineering Safety Section and leader of the ISSC. 'The creation of the ISSC represents the culmination of three decades of the IAEA's active and recognized involvement in this matter through the development of an updated set of safety standards and the assistance to Member States for their application.' To further seismic safety at nuclear installations worldwide, the ISSC will: - Promote knowledge sharing among the international community in order to avoid or mitigate the consequences of extreme seismic events on nuclear installations; - Support countries through advisory services and training courses; and - Enhance seismic safety by utilizing experience gained from previous seismic events in member states. The centre is supported by a scientific committee of high-level experts from academic, industrial and nuclear safety authorities that will advise the ISSC on implementation of its programme. Experts have been nominated from seven specialized areas, including geology and tectonics, seismology, seismic hazard, geotechnical engineering, structural engineering, equipment, and seismic risk. Japan and the United States have both contributed initial funds for creation of the centre, which will be based at

IAEA Sends International Fact-finding Expert Mission to Japan

International Nuclear Information System (INIS)

2011-01-01

Full text: The International Atomic Energy Agency will dispatch an international expert fact-finding mission to Japan. Based upon the agreement between the IAEA and the Government of Japan, the mission, comprising nearly 20 international and IAEA experts from a dozen countries, will visit Japan between 24 May and 2 June 2011. Under the leadership of Mr. Mike Weightman, HM Chief Inspector of Nuclear Installations of the United Kingdom, the mission will conduct fact-finding activities at Tokyo Electric Power Company's Fukushima Dai-ichi Nuclear Power Station (NPS) site and in other locations. The expert mission will make a preliminary assessment of the safety issues linked with TEPCO's Fukushima Dai-ichi NPS accident following the Great East Japan Earthquake and Tsunami. During the mission, areas that need further exploration or assessment based on the IAEA safety standards will also be identified. In the course of the IAEA mission, the international experts will become acquainted with the Japanese lessons learned from the accident and will share their experience and expertise in their fields of competence with the Japanese authorities. Mr. Weightman will present the mission's report at the Ministerial Conference on Nuclear Safety organised by the IAEA in Vienna from 20 to 24 June 2011, as an important input in the process of reviewing and strengthening the global nuclear safety framework that will be launched by the Conference. (IAEA)

Directory of IAEA databases

International Nuclear Information System (INIS)

1991-11-01

The first edition of the Directory of IAEA Databases is intended to describe the computerized information sources available to IAEA staff members. It contains a listing of all databases produced at the IAEA, together with information on their availability

IAEA completes third mission to Kashiwazaki-Kariwa nuclear power plant

International Nuclear Information System (INIS)

2008-01-01

Full text: An IAEA-led team of international experts has completed its third mission, at the invitation of the Government of Japan. This follow-up mission continued to share the lessons learned from the effects of the July 2007 earthquake of the Kashiwazaki- Kariwa nuclear power plant. The mission received further evidence confirming the findings of previous missions regarding the safe performance of the plant during and after the earthquake. The mission found that there is consensus in the scientific community about the causes of the unexpectedly large ground motions experienced at the plant site during the July 2007 earthquake and, consequently, it has been possible to identify the precautions needed to be taken in relation to possible future events. These precautions were based on extensive studies and assessments conducted by a number of specialized institutions and experts in different fields. The necessary upgrades and actions were consequently defined and are being implemented by the Japanese utility for both safety and non-safety related components at the nuclear power plant. The lessons learned from the Kashiwazaki-Kariwa experience has also contributed to the development of IAEA Safety Standards related to seismic safety. These standards are expected to be released shortly. The mission's report will be provided to the Japanese Nuclear and Industrial Safety Agency (NISA) and will be made publicly available in January 2009. The IAEA conducted two previous missions to the Kashiwazaki-Kariwa NPP in August 2007 and January/February 2008. The experience from recent strong seismic events and the lessons learned through the missions to Kashiwazaki-Kariwa NPP have led to the establishment of an International Seismic Safety Centre (ISSC) at the IAEA that is working as a focal point for seismic safety- related information about nuclear installations. Related Resources: (1) January 2008 IAEA Report: Follow-up IAEA Mission in Relation to the Findings and Lessons

IAEA TECDOC 055 Outline

Energy Technology Data Exchange (ETDEWEB)

Shull, Doug [Gregg Protection Services, Palm Beach Gardens, FL (United States)

2015-07-13

An outline of suggestions for updating a version of IAEA-TECDOC-1276 is provided. This update will become IAEA-TECDOC-055, titled ''IAEA handbook for designing and implementing physical protection systems for nuclear material and nuclear facilities.''

IAEA Completes First Ever Corporate Safety Review, at Czech Republic's CEZ

International Nuclear Information System (INIS)

2013-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) today completed a review of corporate safety performance at CEZ a.s., the largest national electricity company in the Czech Republic. For the first time since the Agency launched its Operational Safety Review Team (OSART) missions in 1982, the team addressed corporate aspects of a company in relation to nuclear safety. The team noted a series of good practices and proposed recommendations to strengthen some safety measures. Assembled at the request of the Government of the Czech Republic, the first ''Corporate OSART'' review, which ran from 30 September to 9 October 2013, addressed corporate aspects necessary to ensure the safe operation of the Dukovany and Temelin Nuclear Power Plants (NPPs). The mission included experts from Finland, France, Romania, USA and the IAEA. OSART services aim to improve operational safety at nuclear facilities by objectively assessing safety performance using the IAEA's Safety Standards and proposing recommendations for improvement where appropriate. The missions serve as a channel to exchange information and experience and provide Member States with good practices. A ''Corporate OSART'' is an OSART mission organized to review those centralized functions of the corporate organization of a utility with multiple nuclear plant sites and conventional plant sites that affect all the operational safety aspects of the nuclear power plants of this utility. ''OSART missions are one of the most important tools of the Agency to ensure better and wider implementation of the IAEA Safety Standards,'' said Denis Flory, Deputy Director General in the IAEA Department of Nuclear Safety and Security. ''Since 1982, we have conducted close to 200 safety review missions around the globe; however, this mission is the first of its kind because we focused on the corporate performance that is a necessity for a safe operation of NPPs,'' Flory added

IAEA safeguards glossary. 2001 ed

International Nuclear Information System (INIS)

2002-01-01

IAEA safeguards have evolved since their inception in the late 1960s. In 1980 the IAEA published the first IAEA Safeguards Glossary (IAEA/SG/INF/l) with the aim of facilitating understanding of the specialized safeguards terminology within the international community. In 1987 the IAEA published a revised edition of the Glossary (IAEA/SG/INF/l (Rev.l)) which took into account developments in the safeguards area as well as comments received since the first edition appeared. Since 1987, IAEA safeguards have become more effective and efficient, mainly through the series of strengthening measures approved by the IAEA Board of Governors during 1992-1997, the Board's approval, in 1997, of the Model Protocol Additional to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards (issued as INFCIRC/540 (Corrected)), and the work, begun in 1999, directed towards the development and implementation of integrated safeguards. The IAEA Safeguards Glossary 2001 Edition reflects these developments. Each of the 13 sections of the Glossary addresses a specific subject related to IAEA safeguards. To facilitate understanding. definitions and, where applicable, explanations have been given for each of the terms listed. The terms defined and explained intentionally have not been arranged in alphabetical order, but their sequence within each section corresponds to the internal relationships of the subject treated. The terms are numbered consecutively within each section and an index referring to these numbers has been provided for ease of reference. The terms used have been translated into the official languages of the IAEA, as well as into German and Japanese. The IAEA Safeguards Glossary 2001 Edition has no legal status and is not intended to serve as a basis for adjudicating on problems of definition such as might arise during the negotiation or in the interpretation of safeguards agreements or additional protocols. The IAEA

IAEA safeguards glossary. 2001 ed

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-06-01

IAEA safeguards have evolved since their inception in the late 1960s. In 1980 the IAEA published the first IAEA Safeguards Glossary (IAEA/SG/INF/l) with the aim of facilitating understanding of the specialized safeguards terminology within the international community. In 1987 the IAEA published a revised edition of the Glossary (IAEA/SG/INF/l (Rev.l)) which took into account developments in the safeguards area as well as comments received since the first edition appeared. Since 1987, IAEA safeguards have become more effective and efficient, mainly through the series of strengthening measures approved by the IAEA Board of Governors during 1992-1997, the Board's approval, in 1997, of the Model Protocol Additional to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards (issued as INFCIRC/540 (Corrected)), and the work, begun in 1999, directed towards the development and implementation of integrated safeguards. The IAEA Safeguards Glossary 2001 Edition reflects these developments. Each of the 13 sections of the Glossary addresses a specific subject related to IAEA safeguards. To facilitate understanding. definitions and, where applicable, explanations have been given for each of the terms listed. The terms defined and explained intentionally have not been arranged in alphabetical order, but their sequence within each section corresponds to the internal relationships of the subject treated. The terms are numbered consecutively within each section and an index referring to these numbers has been provided for ease of reference. The terms used have been translated into the official languages of the IAEA, as well as into German and Japanese. The IAEA Safeguards Glossary 2001 Edition has no legal status and is not intended to serve as a basis for adjudicating on problems of definition such as might arise during the negotiation or in the interpretation of safeguards agreements or additional protocols. The IAEA

IAEA safeguards glossary. 2001 ed

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-06-01

IAEA safeguards have evolved since their inception in the late 1960s. In 1980 the IAEA published the first IAEA Safeguards Glossary (IAEA/SG/INF/l) with the aim of facilitating understanding of the specialized safeguards terminology within the international community. In 1987 the IAEA published a revised edition of the Glossary (IAEA/SG/INF/l (Rev.l)) which took into account developments in the safeguards area as well as comments received since the first edition appeared. Since 1987, IAEA safeguards have become more effective and efficient, mainly through the series of strengthening measures approved by the IAEA Board of Governors during 1992-1997, the Board's approval, in 1997, of the Model Protocol Additional to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards (issued as INFCIRC/540 (Corrected)), and the work, begun in 1999, directed towards the development and implementation of integrated safeguards. The IAEA Safeguards Glossary 2001 Edition reflects these developments. Each of the 13 sections of the Glossary addresses a specific subject related to IAEA safeguards. To facilitate understanding. definitions and, where applicable, explanations have been given for each of the terms listed. The terms defined and explained intentionally have not been arranged in alphabetical order, but their sequence within each section corresponds to the internal relationships of the subject treated. The terms are numbered consecutively within each section and an index referring to these numbers has been provided for ease of reference. The terms used have been translated into the official languages of the IAEA, as well as into German and Japanese. The IAEA Safeguards Glossary 2001 Edition has no legal status and is not intended to serve as a basis for adjudicating on problems of definition such as might arise during the negotiation or in the interpretation of safeguards agreements or additional protocols. The IAEA

IAEA safeguards glossary. 2001 ed

International Nuclear Information System (INIS)

2002-01-01

IAEA safeguards have evolved since their inception in the late 1960s. In 1980 the IAEA published the first IAEA Safeguards Glossary (IAEA/SG/INF/l) with the aim of facilitating understanding of the specialized safeguards terminology within the international community. In 1987 the IAEA published a revised edition of the Glossary (IAEA/SG/INF/l (Rev.l)) which took into account developments in the safeguards area as well as comments received since the first edition appeared. Since 1987, IAEA safeguards have become more effective and efficient, mainly through the series of strengthening measures approved by the IAEA Board of Governors during 1992-1997, the Board's approval, in 1997, of the Model Protocol Additional to the Agreement(s) between State(s) and the International Atomic Energy Agency for the Application of Safeguards (issued as INFCIRC/540 (Corrected)), and the work, begun in 1999, directed towards the development and implementation of integrated safeguards. The IAEA Safeguards Glossary 2001 Edition reflects these developments. Each of the 13 sections of the Glossary addresses a specific subject related to IAEA safeguards. To facilitate understanding. definitions and, where applicable, explanations have been given for each of the terms listed. The terms defined and explained intentionally have not been arranged in alphabetical order, but their sequence within each section corresponds to the internal relationships of the subject treated. The terms are numbered consecutively within each section and an index referring to these numbers has been provided for ease of reference. The terms used have been translated into the official languages of the IAEA, as well as into German and Japanese. The IAEA Safeguards Glossary 2001 Edition has no legal status and is not intended to serve as a basis for adjudicating on problems of definition such as might arise during the negotiation or in the interpretation of safeguards agreements or additional protocols. The IAEA

Implementation of the k0-standardization Method for an Instrumental Neutron Activation Analysis: Use-k0-IAEA Software as a Demonstration

International Nuclear Information System (INIS)

Chung, Yong Sam; Moon, Jong Hwa; Kim, Sun Ha; Kim, Hark Rho; Ho, Manh Dung

2006-03-01

Under the RCA post-doctoral program, from May 2005 through February 2006, it was an opportunity to review the present work being carried out in the Neutron Activation Analysis Laboratory, HANARO Center, KAERI. The scope of this research included: a calibration of the counting system, a characterization of the irradiation facility ,a validation of the established k o -NAA procedure.The k o -standardization method for an Neutron Activation Analysis(k o -NAA), which is becoming increasingly popular and widespread,is an absolute calibration technique where the nuclear data are replaced by compound nuclear constants which are experimentally determined. The k o -IAEA software distributed by the IAEA in 2005 was used as a demonstration for this work. The NAA no. 3 irradiation hole in the HANARO research reactor and the gamma-ray spectrometers No. 1 and 5 in the NAA Laboratory were used

IAEA Response and Assistance Network. Date Effective: 1 September 2013

International Nuclear Information System (INIS)

2013-01-01

The Parties to the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the 'Assistance Convention') have undertaken to cooperate between themselves and with the IAEA to facilitate the timely provision of assistance in the case of a nuclear accident or radiological emergency, in order to mitigate its consequences. In September 2000, the General Conference of the IAEA, in resolution GC(44)/RES/16, encouraged Member States ''to implement instruments for improving their response, in particular their contribution to international response, to nuclear and radiological emergencies'' as well as ''to participate actively in the process of strengthening international, national and regional capabilities for responding to nuclear and radiological emergencies and to make those capabilities more consistent and coherent''. As part of the IAEA's strategy for supporting the practical implementation of the Assistance Convention, in 2000 the IAEA Secretariat established a global Emergency Response Network (ERNET) of teams suitably qualified to respond to nuclear or radiological emergencies rapidly and, in principle, on a regional basis. The IAEA Secretariat published IAEA Emergency Response Network - ERNET (EPR-ERNET) in 2000, which set out the criteria and requirements to be met by members of the network. An updated edition was published in 2002. The Second Meeting of the Representatives of Competent Authorities Identified under the Convention on Early Notification of a Nuclear Accident and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, held in Vienna in June 2003, recommended that the IAEA Secretariat convene a Technical Meeting to formulate recommendations aimed at improving participation in the network. Participants in a Technical Meeting held in March 2004 developed a new concept for the network and a completely new draft of the publication. In July 2005, the Third Meeting of Competent Authorities

Now and future of IAEA

International Nuclear Information System (INIS)

Taniguchi, Tomihiro; Omoto, Akira; Ichimura, Tomoya

2005-01-01

IAEA was established in 1957. Main activities consist of safeguards, cooperation of technologies and safety security. It has six sections such as the cooperation of technologies, nuclear energy, safety standards and security, nuclear science and its application, selfguards and management. Eleven Japanese are working in it and they .reported the present activities, problems and the future. Their subjects contain the problems of IAEA and expectation to Japanese, the utilization of nuclear energy, increasing nuclear safety and security in the world, application of radiation and isotope technologies, change and prospect of cooperation of technologies, and non-proliferation and safeguards. It was concluded as a first country holding many nuclear facilities that Japan had not nuclear materials and development activity in hiding and did not transform nuclear fuels reported to weapons. Accordingly, Japan is expected to make effort leading nuclear use for peace and non-proliferation in the world. (S.Y.)

Joint IAEA/NEA IRS guidelines

International Nuclear Information System (INIS)

1997-01-01

The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants

Radioactive waste management services. Safety and technical advisory services available from the IAEA

International Nuclear Information System (INIS)

2000-09-01

This brochure provides updated information about the services and assistance the International Atomic Energy Agency (IAEA) is able to render, upon request by Member States, in the area of radioactive waste management. The ultimate objective is to ensure that all wastes are managed safely and in a way which protects both individual and the environment, now and in the future. The IAEA is the sole global international organization with the statutory authority to establish safety standards for the protection of health against exposure to ionizing radiation. These include safety standards for radioactive waste management. A comprehensive set of such standards is being established, and continuously updated, under the Agency's aegis, which lay out the requirements for the safe management of all types of radioactive waste. The Agency has a further statutory obligation ro provide for the application of these standards at the request of States. The safety of radioactive waste management is not attainable through safety standards alone but requires special technology. An additional function of the IAEA is thus to foster the transfer of technology among States, including the specific technology needed to ensure safe radioactive waste management

IAEA activities in the field of research reactors safety

International Nuclear Information System (INIS)

Ciuculescu, C.; Boado Magan, H.J.

2004-01-01

IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities will be presented: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOC's); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors adopted by the Board of Governors on 8 March 2004, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors published on the IAEA website on February 2003 and the results obtained. (author)

IAEA news: • Newcomer countries face common challenges in nuclear infrastructure development. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators. • IAEA reaches milestone in disposal of radioactive sources

International Nuclear Information System (INIS)

Kollar, Lenka; Dyck, Elisabeth; Dixit, Aabha; Gaspar, Miklos; Gil, Laura

2016-01-01

• Newcomer countries face common challenges in nuclear infrastructure development: Countries embarking on a nuclear power programme need to make sure that the development of their legal, regulatory and support infrastructure keeps pace with the construction of the power plant itself. This is the only way to ensure that the programme proceeds in a safe, secure and sustainable way, concluded participants of a workshop on nuclear power infrastructure development hosted at the IAEA last February. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators: A new generation of advanced, prefab nuclear power reactors called small modular reactors (SMRs) could be licensed and hit the market as early as 2020, and the IAEA is helping regulators prepare for their debut. In a series of workshops that began earlier this year, the IAEA is working closely with regulators on approaches to safety and licensing ahead of potential SMR deployment worldwide. • IAEA reaches milestone in disposal of radioactive sources: Successful tests of a promising technology for moving and storing low level radioactive sealed sources are paving the way for a new disposal method for dealing with small volumes of radioactive waste around the world. The method, which involves placing and covering sealed sources in a narrow hole a few hundred metres deep, would allow countries to safely and securely take charge of their own disused radioactive sources. The proof of concept for the technology was tested in Croatia late last year — without the use of actual radioactive material.

Strengthening the infrastructure for RI applications in cooperation with the IAEA

Energy Technology Data Exchange (ETDEWEB)

Park, Kyung Bae; Hong, Young Don; Kim, Seung Yun; Kim, Kyoung Pyo; Lee, Jeong Kong

2000-12-01

The future direction for nuclear cooperation should be implemented with the aim of enhancing the status of Korea within the international society as well as carrying out the established national nuclear policy goal. Strategies for implementing cooperation with the IAEA were described into four separate parts; 'strategies for strengthening cooperation in general areas', 'strategies for implementing IAEA technical cooperation programs', 'strategies for implementing IAEA CRP programs' and 'Strategies for effective participation in the area of radiation and RI application'. As for strategies for implementing IAEA technical cooperation programs, i) expanding domestic personnel's entering into the IAEA ii) establishment of a liaison office for support of IAEA technical cooperation iii) expanding domestic experts entering into member of consultation group for a director-general of the IAEA and more participation in the international meetings iv) cooperation with IAEA's Seibersdorf Laboratories. For the strengthening of IAEA technical cooperation, strategies for effective implementation of technical cooperation programs such as i) strengthening role of national TC liaison officer ii) strengthening application of Model Project concept iii) Implementing End-user oriented programs iv) Establishment of measure to increase the TC implementation rate v) hosting of fellowship, scientific visitors, support for expert mission, were presented. Strategies for expanding domestic participation in the IAEA technical cooperation programs were also described for producing the benefits from implementing the IAEA technical cooperation programs. As for strategies for implementing the IAEA CRP programs, i) measures for active participation in the IAEA CRP programs and ii) measures for gradual participation in the IAEA CRP programs were separately described. To maximize the utilization of HANARO, a multi-purpose research reactor, the on

Strengthening the infrastructure for RI applications in cooperation with the IAEA

International Nuclear Information System (INIS)

Park, Kyung Bae; Hong, Young Don; Kim, Seung Yun; Kim, Kyoung Pyo; Lee, Jeong Kong

2000-12-01

The future direction for nuclear cooperation should be implemented with the aim of enhancing the status of Korea within the international society as well as carrying out the established national nuclear policy goal. Strategies for implementing cooperation with the IAEA were described into four separate parts; 'strategies for strengthening cooperation in general areas', 'strategies for implementing IAEA technical cooperation programs', 'strategies for implementing IAEA CRP programs' and 'Strategies for effective participation in the area of radiation and RI application'. As for strategies for implementing IAEA technical cooperation programs, i) expanding domestic personnel's entering into the IAEA ii) establishment of a liaison office for support of IAEA technical cooperation iii) expanding domestic experts entering into member of consultation group for a director-general of the IAEA and more participation in the international meetings iv) cooperation with IAEA's Seibersdorf Laboratories. For the strengthening of IAEA technical cooperation, strategies for effective implementation of technical cooperation programs such as i) strengthening role of national TC liaison officer ii) strengthening application of Model Project concept iii) Implementing End-user oriented programs iv) Establishment of measure to increase the TC implementation rate v) hosting of fellowship, scientific visitors, support for expert mission, were presented. Strategies for expanding domestic participation in the IAEA technical cooperation programs were also described for producing the benefits from implementing the IAEA technical cooperation programs. As for strategies for implementing the IAEA CRP programs, i) measures for active participation in the IAEA CRP programs and ii) measures for gradual participation in the IAEA CRP programs were separately described. To maximize the utilization of HANARO, a multi-purpose research reactor, the on-going development and development project are actively

Improvements to the IAEA`s electric generation expansion model

Energy Technology Data Exchange (ETDEWEB)

Stoytchev, D; Georgiev, S [Committee of Energy, Sofia (Bulgaria)

1997-09-01

This paper deals with the implementation of the IAEA`s planning approach and software in Bulgaria. The problems encountered in the process are summarized, with emphasis on two of the limitations of the electric generation expansion model (WASP). The solutions found by Bulgarian experts to overcome these problems are also described, together with some comparative results of the tests performed. (author).

IAEA/SSDL intercomparison of calibration factors for therapy level ionization chambers

International Nuclear Information System (INIS)

Lu Jilong; Cheng Jinsheng; Guo Zhaohui; Li Kaibao

2005-01-01

Objective: By participating in IAEA-SSDL intercomparison, a dose to water calibration factor was introduced in order to check the measuring accuracy of 60 Co radiotherapy dose level standard and ensure the reliability and consistency of our calibration. Methods: The authors carried out both air kerma and absorbed dose to water calibrations against 60 Co γ-rays for one of our field class ionization chambers, and sent the results together with the chamber to IAEA dosimetry laboratory for calibration, then IAEA calibrated it and gave the deviation of the intercomparison. Results: The deviation of our air kerma calibration factors is -0.5%, and the deviation of our absorbed dose to water calibration factors is 0.4%. Conclusion: The deviation of calibration factors between IAEA and SSDL should be no more than ±1.5%. Therefore, the result of this intercomparison is considered satisfactory. (authors)

IAEA/ WHO TLD postal dose intercomparison results in Bangladesh

International Nuclear Information System (INIS)

Mollah, A.S.; Bhuiyan, N.U.; Rahman, S.

2001-01-01

Full text: For the accurate delivery of prescribed dose to the patients, high precision and accuracy in radiation dosimetry is required. The hospital/medical physicist is responsible for the accurate delivery of whole planned radiation doses to the patients prescribed by the radio therapist. The proper delivery of radiation doses depends upon the accurate output measurements of doses from the therapy machines. In Bangladesh, only six 60 Co units and five deep therapy machines are in use. Some more are expected to be installed soon. Still in 2001, none of the Government radiotherapy centers in Bangladesh was properly equipped with medical physicists as well as radiotherapy dosimetry equipment. Bangladesh Atomic Energy Commission (BAEC) is responsible for radiation safety in Bangladesh and BAEC has assigned Secondary Standard Dosimetry Laboratory (SSDL) of Bangladesh for providing dosimetry calibration to all radiotherapy centers in Bangladesh. The output measurements of therapy machines are performed once in a year by SSDL and the results are compared by participating in the annual TLD postal dose intercomparison program organized by IAEA/WHO SSDL Network. The absorbed dose to water is determined using IAEA dosimetry protocol (TRS 277 and 381) and water phantom of size 30 x 30 x 30 cm 3 , The measurements of SSDL are traceable to NPL of UK. The accuracy achieved in SSDL, Bangladesh has been found better than ± 3.5%, which is within the prescribed limit of dosimetry standard of IAEA. The methodology of output dose measurements in different radiotherapy centers in Bangladesh is described along with the IAEA/WHO intercomparison results

IAEA fifty years: more than just safeguards. Interview with Professor Werner Burkart

International Nuclear Information System (INIS)

Anon.

2007-01-01

Professor Werner Burkart, IAEA Deputy Director General and head of the Nuclear Sciences and Applications Division, comments upon matters associated with the fiftieth anniversary of the International Atomic Energy Agency (IAEA). The Agency was founded on July 29, 1957. Today it is a worldwide organization of the United Nations with 144 member countries and manifold duties in the field of nuclear power utilization. The mandate of IAEA is based on the 'Atoms for Peace' initiative, its essence being support of all member countries in the use of nuclear power as long as IAEA safeguards on the spot ensure that no military aims are pursued in those activities. The safeguards work serves to prevent military uses. IAEA recommendations for a global nuclear safety culture, the so-called Safety Standards, are employed by member countries as a basis of legislation and ordinances. The emerging renaissance of nuclear power will be accompanied by the IAEA especially with regard to the important aspects of harmonization, safeguards, safety, security, and readiness for emergencies. The interview took place in Vienna on September 20, 2007. The questions were asked by the President of the Swiss Nuclear Forum, Dr. Bruno Pellaud, former Deputy Director General of IAEA. (orig.)

Summary Report from the Technical Meeting Toward a New Evaluation of Neutron Standards, 8-12 July 2013, IAEA, Vienna

International Nuclear Information System (INIS)

Pronyaev, V.G.; Carlson, A.D.; Capote Noy, R.

2013-07-01

Updated standards evaluations for national cross section libraries (e.g. ENDF/B, JENDL, CENDL and JEFF) are needed as new versions of those libraries are anticipated. Also improvements made in the database and evaluation techniques for the standards can suggest that a new version of a library should be undertaken. A collaboration supported by an IAEA Data Development Project, was established in 2008 after the completion of the last standards evaluation in 2006. Before this project was initiated, there were very long periods between standards evaluations that can now be significantly shortened. The anticipation is that a new standards evaluation can be available whenever one is needed by a major evaluation library. The main objectives of this project are to continuously and critically review new experiments for inclusion in the standards database, and to consider extensions in energy of some of the standards. Other goals are to study improved evaluation procedures and codes for performing the evaluations, maintain those codes, and investigate inclusion of reference data that are not as well-known as the standards but are being widely used as reference in relative measurements of certain types of cross sections. Also included is an effort to improve evaluations of 235 U thermal and 252 Cf spontaneous fission neutron spectra. (author)

IAEA Leads Operational Safety Mission To Gravelines Nuclear Power Plant, France

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA-led international team of experts today began an in-depth operational safety review of the Gravelines Nuclear Power Plant in France. The review, conducted at the invitation of the French government, focuses on programmes and activities essential to the safe operation of the nuclear power plant. The three-week review will cover the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. The conclusions of the review will be based on the IAEA Safety Standards and on well-established international good practices. The mission is not a regulatory inspection, a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team, led by the IAEA's Division of Nuclear Installation Safety, comprises experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain and Ukraine. The Gravelines mission is the 173rd conducted as part of the IAEA's Operational Safety Review Team programme, which began in 1982. France participates actively in the programme and the Gravelines mission is the 24th hosted by the country. General information about OSART missions can be found on the IAEA Website: OSART Missions. (IAEA)

Feasibility study on the establishment of the IAEA international nuclear university

International Nuclear Information System (INIS)

Lee, E. J.; Kim, Y. T.; Nam, Y. M. and others

2002-09-01

The purpose of this project is to support 2002-2003 the IAEA project D.4.0.2, facilitating education, training and research in nuclear science and related fields, especially for a feasibility study on the establishment of the Agency sponsored International Nuclear University. Through this project, the abstract principle for a feasibility study on the establishment of the Agency sponsored International Nuclear university, which contains the new concepts and its objectives, principles to achieve the objectives, its curriculum outline and operation system, suggested project activities, was developed and submitted to the Agency. The Korean proposal were presented several times at the IAEA meetings and other international meetings related nuclear human resources development for understanding the necessity of a feasibility study on the establishment of the Agency sponsored international nuclear university with Member States. And the Korean proposal included such as the organization of a worldwide network using information and communication technology among Merber States' research institutes and training/education centers, curriculum outline and operation system of the INU will be produced. Also for further cooperation of the IAEA INU project implementation with the Agency, hosting IAEA INIS mirror site, establishment of the RCA region office, establishment of the INTEC at the Korean Atomic Energy Research Institute, and advanced curriculum of nuclear technology linked with NT, BT, ET, IT were made progress as a part of conceptualizing of the IAEA project

IAEA Clarification on Syria

International Nuclear Information System (INIS)

2011-01-01

Full text: Director General Amano has been quoted in a news story as saying today that a site in Syria allegedly destroyed by Israel was a nuclear reactor under construction. The Director General did not say that the IAEA has reached the conclusion that the site was definitely a nuclear reactor. The IAEA continues to seek further information on the nature of the Dair Alzour site. (IAEA)

Relevant documents to IAEA regulations for the safe transport of radioactive materials

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.; Sabek, M.G.; Gomma, M.

1998-01-01

IAEA regulations for the safe transport of radioactive materials provide standards for insuring a high level of safety of people, property, and environment against radiation, contamination, and criticality hazards as well as thermal effects associated with the transport of radioactive materials. IAEA routinely publishes technical reports which are relevant to radioactive material transportation such as INTERTRAN, directory of transport packaging test facilities, and others. A case study was performed to assess the impact of transporting radioactive materials through the suez canal using the two computer codes namely INTERTRAN and RADTRAN-4 which are part of IAEA technical documents. A comparison of the results of these two codes is given

International movement on radiation safety related to the ICRP and the IAEA-RADWASS

International Nuclear Information System (INIS)

Kosako, Toshiso

1994-01-01

Nowadays discussion on Radiation Safety has a spread of world wide range. The main framework on radiation safety was constructed by ICRP (International Commission on Radiological Protection), which was established in 1928. This term of the committee was from June 1993 to May 1997 and the first plenary meeting was held at the Queen's hotel in Bournemouth of the United Kingdom on September 1993. The outline of this meeting, especially related items to the Committee 4, were summarized in this paper. The second point of our workshop considerations is radioactive waste problems, which are now under discussion in RADWASS (Radioactive Waste Safety Standards) project of IAEA (International Atomic Energy Agency). This IAEA-RADWASS will last nearly 10 years to cover whole subjects. These discussed items are arranged into various international standards; the safety fundamental, the safety standards, the safety guides and the safety practices. These systematic approach, if we could summarize, would be effective not only to the specialists but also to a general public to get an acceptance of radioactive waste problem. Here, this IAEA-RADWASS project is reviewed. (author)

Statement to the forty-fourth regular session of the IAEA General Conference 2000. IAEA General Conference. Vienna, 18 September 2000

International Nuclear Information System (INIS)

ElBaradei, M.

2000-01-01

In his Statement on the forty-fourth regular session of the General Conference of the IAEA, the Director General of the Agency highlighted IAEA's achievements in connection with its major functions: as catalyst for the development and transfer of nuclear technology (nuclear power, nuclear fuel cycle and waste management, preservation of nuclear expertise, nuclear science and applications, laboratory and research activities, future challenges in nuclear technology), as a recognized authority on nuclear safety (international conventions, establishment of international standards, safety services, early shutdown of nuclear power plants, decommissioning issues, Kursk submarine accident, future challenges in nuclear safety), and as an instrument for the verification of nuclear non-proliferation (safeguards agreements and additional protocols, implementation of United Nations Security Council Resolutions relating to Iraq, safeguards agreement with the Democratic People's Republic of Korea, application of IAEA Safeguards in the Middle East, other verification activities, security of material, future challenges in verification. He also discussed the Agency's technical co-operation programme and the Agency management for maximum efficiency and effectiveness, and the new outreach policy

IAEA Director General reacts to U.S.- India cooperation agreement

International Nuclear Information System (INIS)

2005-01-01

Full text: IAEA Director General, Mohamed ElBaradei has welcomed the US-India agreement to embark on full civil nuclear energy cooperation and to work to enhance nuclear non-proliferation and security. 'Out of the box thinking and active participation by all members of the international community are important if we are to advance nuclear arms control, non-proliferation, safety and security, and tackle new threats such as illicit trafficking in sensitive nuclear technology and the risks of nuclear terrorism,' Dr. ElBaradei said. Dr. ElBaradei has also been urging all countries using nuclear energy to apply the highest safety standards possible. 'Making advanced civil nuclear technology available to all countries will contribute to the enhancement of nuclear safety and security,' he said. Dr. ElBaradei said that India's intention to identify and place all its civilian nuclear facilities under IAEA safeguards and sign and adhere to an Additional Protocol with respect to civilian nuclear facilities is a welcome development. I have always advocated concrete and practical steps towards the universal application of IAEA safeguards,' Dr. ElBaradei said. (IAEA)

The IAEA Safety Regime for Decommissioning

International Nuclear Information System (INIS)

Bell, M.J.

2002-01-01

Full text of publication follows: The International Atomic Energy Agency is developing an international framework for decommissioning of nuclear facilities that consists of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, and a hierarchy of Safety Standards applicable to decommissioning. The Joint Convention entered into force on 18 June 2001 and as of December 2001 had been ratified by 27 IAEA Member States. The Joint Convention contains a number of articles dealing with planning for, financing, staffing and record keeping for decommissioning. The Joint Convention requires Contracting Parties to apply the same operational radiation protection criteria, discharge limits and criteria for controlling unplanned releases during decommissioning that are applied during operations. The IAEA has issued Safety Requirements document and three Safety Guides applicable to decommissioning of facilities. The Safety Requirements document, WS-R-2, Pre-disposal Management of Radioactive Waste, including Decommissioning, contains requirements applicable to regulatory control, planning and funding, management of radioactive waste, quality assurance, and environmental and safety assessment of the decommissioning process. The three Safety Guides are WS-G-2.1, Decommissioning of Nuclear Power Plants and Research Reactors, WS-G-2.2, Decommissioning of Medical, Industrial and Research Facilities, an WS-G-2.4, Decommissioning of Nuclear Fuel Cycle Facilities. They contain guidance on how to meet the requirements of WS-R-2 applicable to decommissioning of specific types of facilities. These Standards contain only general requirements and guidance relative to safety assessment and do not contain details regarding the content of the safety case. More detailed guidance will be published in future Safety Reports currently in preparation within the Waste Safety Section of the IAEA. Because much material arising during the decommissioning

Approaches for increasing the cooperation between Member States and IAEA under SSS

International Nuclear Information System (INIS)

Rheem, Karp-Soon; Park, Wan-Sou; Kim, Byung-Koo

1997-01-01

With introduction of the Strengthened Safeguards System (SSS), both the IAEA and Member States are concerned about the limited resources to carry out the SSS activity and the potential increase of additional cost and burdens. Even though the IAEA has recently prepared a procedure of the generalized New Partnership Approach (NPA), its wider application to the general Member States is difficult at the present time. For the generalized NPA necessitates that SSACs of the Member States have sufficient technical capability in safeguards to carry out the necessary activities. Unfortunately a few Member States seem to be qualified to have the sufficient technical capability that the IAEA desires. In this topic, a new approach to increase the cooperation between Member States and IAEA under SSS is proposed such that effective supports can be provided to all of its Member States that are not technically competent in terms of safeguards experience. This is realized by so called 'tunneling effort', meaning that desired goals are accomplished by efforts from both Member States and the IAEA. The Member States having high technical competence in safeguards provide technical assistance to the Member States that are not competent until they attain to a certain level in technical capability, while the IAEA provides the guidelines, and coordinates the process. The formal introduction of the Quality Control concept to the safeguards management is proposed as well so as to efficiently reduce burdens from the implementation of the SSS. (author)

Evaluating and integrating corporate social responsibility standards: Implications for CSR concepts

Directory of Open Access Journals (Sweden)

Markus Stiglbauer

2012-03-01

Full Text Available Standards play a major role when concepts of corporate social responsibility (CSR ought to be implemented and corporate social performance (CSP ought to be assessed. Ethical reasoning and stakeholders’ expectations help to measure companies’ intentions to implement CSR standards and to measure their efficiency. With different standards of CSR (company standards, industry standards, multi-stakeholder standards and independent standards companies may implement we categorize and еvaluate those standards and give advice which opportunities but also threats may arise for companies when implementing such codes within firm-specific CSR concepts. We suggest a combination of different standards and replenish them with firm-specific codes of conduct.

The management of low activity radioactive waste: IAEA guidance and perspectives

International Nuclear Information System (INIS)

Louvat, D.; Rowat, J.H.; Potier, J.M.

2005-01-01

This paper describes the safety standards and reports of the International Atomic Energy Agency (IAEA) applicable to the management and disposal of low activity radioactive waste and provides some historical perspective on their development. Some of the most important current issues in the area of low activity radioactive waste management are discussed in the context of related ongoing IAEA activities. At the end of the paper, a number of issues and questions are raised for consideration and discussion at this symposium. (author)

IAEA activities on education and training in radiation and waste safety: Strategic approach for a sustainable system

International Nuclear Information System (INIS)

Mrabit, Khammar; Sadagopan; Geetha

2003-01-01

The statutory safety functions of the International Atomic Energy Agency (IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place enabling the Government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. The IAEA education and training activities follows the resolutions of its General Conferences and reflects the latest IAEA standards and guidance. In response to GC(44)/RES/13, the IAEA prepared a 'Strategic Approach to Education and Training in Radiation and Waste Safety' aiming at establishing, by 2010, sustainable education a training programmes in Member States. This Strategy was endorsed by General Conference resolution GC(45)/RES/10C that, inter alia, urged the Secretariat to implement the Strategy on Education and Training and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States' national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. In the last General Conference 2002, the IAEA was urged to continue to implement the Strategy, including the convening of the Steering Committee. The first Technical Committee meeting took place during the week 25-29 November 2002. (author)

IAEA monitoring field trials workshop

International Nuclear Information System (INIS)

Ross, H.H.; Cooley, J.N.; Belew, W.L.

1995-01-01

Recent safeguards inspections in Iraq and elsewhere by the International Atomic Energy Agency (IAEA) have led to the supposition that environmental monitoring can aid in verifying declared and in detecting undeclared nuclear activities or operations. This assumption was most recently examined by the IAEA's Standing Advisory Group on Safeguards Implementation (SAGSI), in their reports to the IAEA Board of Governors. In their reports, SAGSI suggested that further assessment and development of environmental monitoring would be needed to fully evaluate its potential application to enhanced IAEA safeguards. Such an inquiry became part of the IAEA ''Programme 93+2'' assessment of measures to enhance IAEA safeguards. In March, 1994, the International Safeguards Group at Oak Ridge hosted an environmental monitoring field trial workshop for IAEA inspectors to train them in the techniques needed for effective environmental sampling. The workshop included both classroom lectures and actual field sampling exercises. The workshop was designed to emphasize the analytical infrastructure needed for an environmental program, practical sampling methods, and suggested procedures for properly planning a sampling campaign. Detailed techniques for swipe, vegetation, soil, biota, and water associated sampling were covered. The overall approach to the workshop, and observed results, are described

Implementation of the k{sub 0}-standardization Method for an Instrumental Neutron Activation Analysis: Use-k{sub 0}-IAEA Software as a Demonstration

Energy Technology Data Exchange (ETDEWEB)

Chung, Yong Sam; Moon, Jong Hwa; Kim, Sun Ha; Kim, Hark Rho [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Ho, Manh Dung [Nuclear Research Institute, Dalat (Viet Nam)

2006-03-15

Under the RCA post-doctoral program, from May 2005 through February 2006, it was an opportunity to review the present work being carried out in the Neutron Activation Analysis Laboratory, HANARO Center, KAERI. The scope of this research included: a calibration of the counting system, a characterization of the irradiation facility ,a validation of the established k{sub o}-NAA procedure.The k{sub o}-standardization method for an Neutron Activation Analysis(k{sub o}-NAA), which is becoming increasingly popular and widespread,is an absolute calibration technique where the nuclear data are replaced by compound nuclear constants which are experimentally determined. The k{sub o}-IAEA software distributed by the IAEA in 2005 was used as a demonstration for this work. The NAA no. 3 irradiation hole in the HANARO research reactor and the gamma-ray spectrometers No. 1 and 5 in the NAA Laboratory were used.

IAEA integrated safeguards instrumentation program (I2SIP)

International Nuclear Information System (INIS)

Arlt, R.; Fortakov, V.; Gaertner, K.J.

1995-01-01

This article is a review of the IAEA integrated safeguards instrumentation program. The historical development of the program is outlined, and current activities are also noted. Brief technical descriptions of certain features are given. It is concluded that the results of this year's efforts in this area will provide significant input and be used to assess the viability of the proposed concepts and to decide on the directions to pursue in the future

IAEA technical committee meeting on research using small fusion devices (abstracts)

International Nuclear Information System (INIS)

1999-12-01

The thirteenth IAEA technical committee meeting on research using small fusion devices are held in Chengdu, P. R. China on 18-20 Oct. , 1999. 41 articles are received and the content includes toroidal systems, helical systems, plasma focus, diagnostic systems, theory and modeling, improving confinement, numerical simulation, innovative concepts and others

An IAEA Survey of Dosimetry Audit Networks for Radiotherapy

International Nuclear Information System (INIS)

Grochowska, Paulina; Izewska, Joanna

2013-01-01

A Survey: In 2010, the IAEA undertook a task to investigate and review the coverage and operations of national and international dosimetry audit programmes for radiotherapy. The aim was to organize the global database describing the activities of dosimetry audit networks in radiotherapy. A dosimetry audit questionnaire has been designed at an IAEA consultants' meeting held in 2010 for organizations conducting various levels of dosimetry audits for radiotherapy. Using this questionnaire, a survey was conducted for the first time in 2010 and repeated in 2011. Request for information on different aspects of the dosimetry audit was included, such as the audit framework and resources, its coverage and scope, the dosimetry system used and the modes of audit operation, i.e. remotely and through on-site visits. The IAEA questionnaire was sent to over 80 organizations, members of the IAEA/WHO Network of Secondary Standards Dosimetry Laboratories (SSDLs) and other organizations known for having operated dosimetry audits for radiotherapy in their countries or internationally. Survey results and discussion: In response to the IAEA survey, 53 organizations in 45 countries confirmed that they operate dosimetry audit services for radiotherapy. Mostly, audits are conducted nationally, however there are five organizations offering audits abroad, with two of them operating in various parts of the world and three of them at the regional level, auditing radiotherapy centres in neighbouring countries. The distribution of dosimetry audit services in the world is given. (author)

The evolution of IAEA safeguards

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-01

This, second in a new series of booklets dealing with IAEA safeguards is intended for persons professionally interested in the subject as government officials responsible for non-proliferation or management of nuclear facilities, and practitioners of safeguards - the international and national officials charged with implementing IAEA safeguards. It is also aimed at the broader public concerned with the spread of nuclear weapons and interested in nuclear arms control and disarmament. It presents the situation as IAEA safeguards make `quantum jump` into new phase characterized by the IAEA as the `Strengthened Safeguards System`. It includes the historical overview of the International safeguards from 1945-1998; the aims and limitations of IAEA Safeguards; a chapter on how safeguards work in practice; as well as new challenges and opportunities

The evolution of IAEA safeguards

International Nuclear Information System (INIS)

1998-01-01

This, second in a new series of booklets dealing with IAEA safeguards is intended for persons professionally interested in the subject as government officials responsible for non-proliferation or management of nuclear facilities, and practitioners of safeguards - the international and national officials charged with implementing IAEA safeguards. It is also aimed at the broader public concerned with the spread of nuclear weapons and interested in nuclear arms control and disarmament. It presents the situation as IAEA safeguards make 'quantum jump' into new phase characterized by the IAEA as the 'Strengthened Safeguards System'. It includes the historical overview of the International safeguards from 1945-1998; the aims and limitations of IAEA Safeguards; a chapter on how safeguards work in practice; as well as new challenges and opportunities

The IAEA intercomparison for individual monitoring

International Nuclear Information System (INIS)

Griffith, R.V.; Boehm, J.; Herrman, D.; Strachotinsky, C.; Thompson, I.M.G.

1990-01-01

In 1985 the International Commission on Radiation Units and Measurements introduced a new set of operational quantities for radiation protection purposes through Report 39. The International Atomic Energy Agency has been concerned with the impact of possible adoption of these quantities by its 113 Member States. Thus the Agency implemented a Coordinated Research Programme on Intercomparison for Individual Monitoring in 1987. The first phase completed with a Research Coordination meeting of the participants in April, 1989. Photon exposures were provided at 11 energies over a range from 18 keV to 1.25 MeV at three standards laboratories in Austria, the GDR and the UK. Technical coordination was provided by the PTB, Braunschweig. Twenty one laboratories from 19 countries participated with film, TLD of various types, and combination dosemeters. Irradiations were performed on the IAEA 30 cm cubic, water-filled phantom that is in use throughout its network of 61 Secondary Standard Dosimetry Laboratories. Conversion coefficients for the IAEA phantom were calculated by the PTB and confirmed through measurements at ASMW in the GDR. Preliminary results indicated that the type of dosemeter (film or TLD) had little effect on the quality of results. The most important factor appears to be the specific techniques used for data interpretation. (author)

Standardized quality audit procedures for on-site dosimetry visits to radiotherapy hospitals. Report of the IAEA consultants' meeting, IAEA, Vienna, 27 September - 1 October 1999; revised in 2001

International Nuclear Information System (INIS)

Izewska, Joanna; Dutreix, A.; Followill, D.S.; Nisbet, A.; Novotny, J.; Sipila, P.; Dam, J. van

2002-01-01

Since 1969 the International Atomic Energy Agency (IAEA), together with the World Health Organization (WHO), has performed postal TLD audits to verify the calibration of radiotherapy beams in developing countries. The IAEA over the past 30 years, has verified the calibration of more than 3500 clinical photon beams at approximately 1000 radiotherapy hospitals. Detailed follow-up procedures have been implemented since 1996. When the TLD result of a participating institution falls outside the acceptance limits of ±5%, the institution is initially informed that there is a discrepancy and requested to try to identify the reasons why it occurred. The institution is not informed of the actual magnitude of the discrepancy (blind conditions) but is offered a second TLD audit. If the deviation cannot be resolved by the local radiotherapy institution or the national SSDL, then an on-site visit is suggested which, if accepted, is made by an IAEA expert in clinical dosimetry. The on-site visit includes a review of the dosimetry data and techniques, corrective measurements and ad-hoc training. The reasons for the discrepancy are then traced, explained, corrected and reported. Until the discrepancies are resolved and changes have been implemented by hospitals to ensure that the discrepancies do not reoccur, the safe and effective delivery of radiation doses to patients is questionable. This document provides a standardised set of procedures for resolving discrepancies during onsite visits to radiotherapy hospitals by the IAEA experts. The table below summarises the acceptance criteria to be used by the IAEA experts for dosimetry and mechanical parameters of the hospital treatment units. If some of the parameters are outside the acceptance criterion, it will not be possible for an institution to assure the adequate quality of the dosimetry practices in radiotherapy. The criteria are based on analyses of clinical data and the measurement uncertainties for various dosimetry and

The US Support Program to IAEA Safeguards Priority of Containment and Surveillance

Energy Technology Data Exchange (ETDEWEB)

Diaz,R.A.

2008-06-13

The United States Support Program (USSP) priority for containment and surveillance (US) focuses on maintaining or improving the reliability and cost-effectiveness of C/S systems for IAEA safeguards, expanding the number of systems that are unattended and remotely monitored, and developing verification methods that help streamline the on-site inspection process. Existing IAEA C/S systems have evolved to become complex, integrated systems, which may include active seals, nondestructive assay (NDA) instruments, video cameras, and other sensors. These systems operate autonomously. They send analytical data to IAEA headquarters where it can be reviewed. These systems present challenges to the goals of improved system performance, standardization, reliability, maintainability, documentation, and cost effectiveness. One critical lesson from past experiences is the need for cooperation and common objectives among the IAEA, the developer, and the facility operator, to create a successful, cost effective system. Recent USSP C/S activities include Rokkasho Reprocessing Plant safeguard systems, production of a new shift register, numerous vulnerability assessments of C/S systems, a conduit monitoring system which identifies tampering of IAEA conduit deployed in the field, fiber optic seal upgrades, unattended monitoring system software upgrades, next generation surveillance system which will upgrade existing camera systems, and support of the IAEA's development of the universal nondestructive assay data acquisition platform.

A study to analyze IAEA planning of 2004-2005 programme and to establish cooperation directions with the IAEA

International Nuclear Information System (INIS)

Oh, K. B.; Lee, K. S.; Lee, B. W.; Ko, H. S.; Ryu, J. S.; Lee, T. J.; Kim, M. R.

2003-07-01

The objective of this study is to utilize the IAEA effectively through reflecting Korea's opinion fully for the planning of the Agency's 2004∼2005 Programme. This study first analyzed the current status of the IAEA Programme and Budget and reviewed the issues relevant to Korea. Second, this study assessed the IAEA 2004∼2005 Programme and drew up Korea's opinion for it. The official document including the opinions was submitted to the Secretariat. In reviewing the Programme, this study considered the strengths of Korea related to the Programme. Also some projects and CRPs, which can be lead by Korea, were proposed. The IAEA 2004∼2005 Programme reflected well the technical and social changes and its structure seems to be proper. The budget was proposed to be increased over 10%, violating the zero-real growth principle. This seems to be inevitable considering the increase of safeguards activities. However, there should be prepared some measures to avoid rapid increase of the burdens of the Member States. In the process of the planning of the IAEA 2004∼2005 Programme, the following points should be emphasized. First, SMR activities should be given a high priority considering the high interests of developing countries and be set up as a separate project as in the 2002∼2003 Programme. Second, more budget should be allocated for Project A.4.04(Support for demonstration of nuclear seawater desalination), considering the highest priority of the project in Program A. Third, it's better to change the title of Subprogram C.3 to 'Nuclear knowledge Preservation' to stick to the original rationale of the subprogram. There is a need for further activities such as establishing and implementing the concept of international nuclear school based on the result of the feasibility study done in 2002∼2003. Fourth, further activities needs to be added to the Project D.2.03 for the efficient conversion to high density, low enriched uranium in Member States; for instance, review

Quality assurance of the French nuclear market - IAEA code and standardization

International Nuclear Information System (INIS)

Pavaux, F.

1980-06-01

The fact that Quality Assurance was imported from abroad and our reticence to reach agreement on single and accurate texts explain, if not excuse, the abundance of reference requirements existing on the French nuclear market with respect to Quality Assurance Programmes. But all is not lost, since the IAEA Good Practice Code is perhaps the solution that, in a few years time, will enable all French industrialists to work and be assessed by their customers, according to the same reference text [fr

Radiation protection and safety of radiation sources international basic safety standards

CERN Document Server

International Atomic Energy Agency. Vienna

2014-01-01

The Board of Governors of the IAEA first approved Basic Safety Standards in June 1962; they were published by the IAEA as IAEA Safety Series No. 9. A revised edition was issued in 1967. A third revision was published by the IAEA as the 1982 Edition of IAEA Safety Series No. 9 ; this edition was jointly sponsored by the IAEA, ILO, OECD/NEA and the WHO. The next edition was International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, published by the IAEA as IAEA Safety Series No. 115 in February 1996, and jointly sponsored by the FAO, IAEA, ILO, OECD/NEA, PAHO and the WHO.

Operational intervention levels for reactor emergencies IAEA recommendations

Energy Technology Data Exchange (ETDEWEB)

Aguiar, Laís A. de; Reis, Arlene A. dos; Santos, Raul dos, E-mail: laguiar@ird.gov.br, E-mail: arlene@ird.gov.br, E-mail: raul@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2017-07-01

The IAEA publication EPR-NPP-OILs-2017, Operational Intervention Levels for Reactor Emergences and Methodology for their Derivation, provides selected default OIL values, describing a methodology for their derivation, as well as practical tools and recommendations for their use. IAEA recommends that tools and default OIL values be directly integrated into national emergency arrangements or reviewed and modified as necessary to meet the specific emergency preparedness and response arrangements. The Institute of Radiation Protection and Dosimetry (IRD) has a Radiological Assessment TEAM (EAR) as pare of its Radiation Emergency Response System. Brazilian regulatory standards address actions for radiation emergencies encompassing necessary measures to assess public exposures, intervention levels to protect the public and recommendations for protective actions as, evacuation, relocation, sheltering and food restrictions. The objective of this paper is to present a discussion the use these OILs, to compare those ones established by the Brazilian standards and to propose a methodology on how OILs can be used by EAR/IRD in case of an emergency at the Brazilian NPP. (author)

Operational intervention levels for reactor emergencies IAEA recommendations

International Nuclear Information System (INIS)

Aguiar, Laís A. de; Reis, Arlene A. dos; Santos, Raul dos

2017-01-01

The IAEA publication EPR-NPP-OILs-2017, Operational Intervention Levels for Reactor Emergences and Methodology for their Derivation, provides selected default OIL values, describing a methodology for their derivation, as well as practical tools and recommendations for their use. IAEA recommends that tools and default OIL values be directly integrated into national emergency arrangements or reviewed and modified as necessary to meet the specific emergency preparedness and response arrangements. The Institute of Radiation Protection and Dosimetry (IRD) has a Radiological Assessment TEAM (EAR) as pare of its Radiation Emergency Response System. Brazilian regulatory standards address actions for radiation emergencies encompassing necessary measures to assess public exposures, intervention levels to protect the public and recommendations for protective actions as, evacuation, relocation, sheltering and food restrictions. The objective of this paper is to present a discussion the use these OILs, to compare those ones established by the Brazilian standards and to propose a methodology on how OILs can be used by EAR/IRD in case of an emergency at the Brazilian NPP. (author)

Approach toward development of release standards for D and D cleanup

International Nuclear Information System (INIS)

Chen, S. Y.

1999-01-01

The release of materials containing residual radioactivity from a controlled environment in decontamination and decommissioning (D and D) activities has been problematic. The primary impediment to such a release is the lack of a suitable framework within which release standards can be developed. The concept of clearance for radioactive materials was recently introduced by the International Atomic Energy Agency (IAEA) (l). This concept is being evaluated by the international regulatory communities as a basis for setting standards for releasing from control solid materials containing residual radioactivity. Accordingly, both the IAEA (2) and the European Commission (EC) (3) have recently proposed clearance standards. In the US, the Nuclear Regulatory Commission (USNRC) has just begun its rule-making process on clearance. The term ''clearance'' was introduced as a regulatory process for releasing radioactive materials posing negligible risks. A trivial risk level has been determined to be a 10 -6 to 10 -7 annual risk to an exposed individual, and a population risk of no more than 0.1 for an annual practice. Under these strict constraints, exposure scenarios would be developed to estimate potential doses to affected individuals. Such scenarios may account for processing, disposal, and product end-use of materials. This paper discusses these scenarios and also describes the technical basis for deriving release levels under the suggested risk for dose constraints

IAEA Nuclear Security - Achievements 2002-2011

International Nuclear Information System (INIS)

2012-03-01

The possibility that nuclear or other radioactive material could be used for malicious purposes is real. This calls for a collective commitment to the control of, and accountancy for, material, as well as to adequate levels of protection in order to prevent criminal or unauthorized access to the material or associated facilities. Sharing of knowledge and experience, coordination among States and collaboration with other international organizations, initiatives and industries supports an effective international nuclear security framework. In 2001, the Board of Governors tasked the IAEA with improving nuclear security worldwide. The report that follows provides an overview of accomplishments over the last decade and reflects the importance that States assign to keeping material in the right hands. The IAEA has established a comprehensive nuclear security programme, described first in the Nuclear Security Plan of 2002-2005 and subsequently in the second plan of 2006- 2009. Activities included developing internationally accepted nuclear security guidance, supporting international legal instruments, protecting material and facilities, securing transport and borders, detecting and interdicting illicit nuclear trafficking, strengthening human resource capacity and preparing response plans should a nuclear security event occur. The IAEA has begun the implementation of its third Nuclear Security Plan, to be completed at the end of 2013. This approach to nuclear security recognizes that an effective national nuclear security regime builds on a number of factors: the implementation of relevant international legal instruments; IAEA guidance and standards; information protection; physical protection; material accounting and control; detection of, and response to, trafficking in such material; national response plans and contingency measures. Implemented in a systematic manner, these building blocks make up a sustainable national nuclear security regime and contribute to global

RCA/IAEA third external dosimetry intercomparison in East Asia

International Nuclear Information System (INIS)

Momose, T.; Yamamoto, H.; Cruz Suarez, R.

2005-01-01

Full text: Several intercomparison exercises were organized by the International Atomic Energy Agency (IAEA) on the determination of operational quantities at the regional or interregional basis. These exercises revealed significant differences in the approach, methods and assumptions, and consequently in the measurement results obtained by participating laboratories. In the East Asia region, the third phase of the Hp(10) intercomparison, organized within the frame of the Regional Cooperation Agreement (RCA) as a follow-up to previous exercises during 1990-92 and 1995-96, was completed mid-2004. The first phase grouped 25 laboratories from 16 member states, and 4 Secondary Standards Dosimetry Laboratories irradiated dosimeters in 6 different qualities for photon and beta radiations. In the second phase, 23 laboratories from 16 member states participated, and 3 Secondary Standards Dosimetry Laboratories provided irradiation in 5 different radiation qualities simulating workplace fields. The results of the second phase for the determination of operational quantities Hp(d) were satisfactory for all participating Member States, with marked improvement from the first phase; the laboratories demonstrated good performance in both quantities tested. These results underline the importance of such an intercomparison programme as a key element towards the harmonization of quantities and units on an international level. This paper presents the results of this RCA/IAEA intercomparison, and also the forthcoming RCA activities supporting intercomparison runs for the assessment of occupational exposure. Member states strongly recommend that the IAEA continue acting as a focal point for, inter alia, training in all forms, particularly in measurements and dosimetry techniques. This exercise also stressed the importance for the IAEA to take an active role in establishing a network of monitoring laboratories for radiation protection purposes, as it would provide for better information

OSART Guidelines. 2015 Edition. Reference Report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2016-01-01

The IAEA works to provide a global nuclear safety and security framework for the protection of people and the environment from the effects of ionizing radiation, the minimization of the likelihood of accidents that could endanger life and property, and effective mitigation of the effects of any such events, should they occur. The strategic approach to achieving such a framework involves continual improvement in four areas: national and international safety infrastructures; the establishment and global acceptance of IAEA safety standards; an integrated approach to the provision for the application of the safety standards; and a global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. Conservative design, careful manufacture and sound construction are all prerequisites for the safe operation of nuclear power plants. However, the safety of the plant also depends ultimately on: sound management, policies, procedures, processes and practices; the capability and reliability of commissioning and operating personnel; comprehensive instructions; sound accident management and emergency preparedness; and adequate resources. Finally, a positive attitude and conscientiousness on the part of all staff in discharging their responsibilities is important to safety. The OSART programme is based on the safety standards applicable to nuclear power plants. IAEA safety standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Group identify important current nuclear safety issues and also serve as references during an OSART review. The publication OSART Guidelines provides overall guidance on the conduct of OSART

IAEA programme to support development and validation of advanced design and safety analysis codes

Energy Technology Data Exchange (ETDEWEB)

Choi, J., E-mail: J.H.Choi@iaea.org [International Atomic Energy Agency, Vienna (Austria)

2013-07-01

The International Atomic Energy Agency (IAEA) has been organized many international collaboration programs to support the development and validation of design and safety analysis computer codes for nuclear power plants. These programs are normally implemented with a frame of Coordinated Research Project (CRP) or International Collaborative Standard Problem (ICSP). This paper introduces CRPs and ICSPs currently being organized or recently completed by IAEA for this purpose. (author)

IAEA yearbook 1996

International Nuclear Information System (INIS)

1996-09-01

Part A of the Yearbook describes the role played by the IAEA in helping to advance sustainable development by the transfer of nuclear and radiation technology. The introduction to this section this year discusses the application of quality assurance practices to this important work. The main article describes new planning procedures that are being adopted to ensure that these technical co-operation activities are of significant and practical benefit to the States concerned. The work routinely carried out by the IAEA on the development and dissemination of nuclear and radiation techniques covers a wide range of subjects - the practical aspects of physics and chemistry, hydrology, industrial applications, human health, and food and agriculture. Part B of the Yearbook concentrates on food irradiation and the use of nuclear monitoring techniques in programmes for improving human nutrition. Part C of the Yearbook deals with nuclear power and its fuel cycle and waste management technology. The section on nuclear power describes developments during 1995 in a wide range of countries. It also details the IAEA's work on the comparative health and environmental impacts of different types of energy systems. Of particular interest this year in the fuel cycle area is the report of the downturn in world uranium activities that has lasted for more than 15 years may be coming to an end. In the waste management section, emphasis is given to the technology of environmental restoration of sites after contamination resulting from past nuclear activities. A discussion of different aspects of the safety of nuclear power and of the uses of radiation is to be found in Part D, The Nuclear Safety Review. As in previous years, Part E of the IAEA Yearbook 1996 deals with the IAEA's major contribution to the non-proliferation regime - international safeguards. Part E also contains a description of IAEA activities designed to assist Member States in preventing trafficking in nuclear materials

Standard characterization of phosphate rock samples from the FAO/IAEA phosphate project

International Nuclear Information System (INIS)

Binh, Truong; Zapata, F.

2002-01-01

Phosphate rocks (PR) are phosphate-bearing minerals that vary widely in their inherent characteristics and consequently their agronomic potential. In the framework of a FAO/IAEA networked research project, the evaluation of the agronomic effectiveness of natural and modified PR products under a variety of soil climate and crop management conditions was carried out. The characterization of phosphate rocks is the first and essential step in evaluating their suitability for direct application. If several PR sources are utilized, standardized methods should be used for comparison purposes to determine their agronomic potential. This paper describes the standard characterization of phosphate rock products utilized in the project, in particular the mineralogical and crystallographic analyses, physical analyses, chemical composition and solubility in conventional reagents. A total of 28 phosphate rock samples from 15 countries were collected and analyzed in specialized laboratories. The data on mineralogy, chemical composition and solubility in conventional reagents are closely interrelated. An arbitrary classification of the reactivity of the PR samples was made based on the solubility indices in conventional reagents. On another hand, the results of the crystallographic parameters, calculated indices of absolute solubility, specific surface and porosity reflect the variability of the physical state and the sample pre-conditioning treatment of the analyzed products. A proper characterization of phosphate rock samples should provide the maximum of basic information that can be obtained in a cost-effective manner in normal chemical laboratories. Based on the results of this characterization, the following determinations are recommended: a description of the sample, major elemental (total P, Ca, Mg) composition, solubility in conventional reagents (neutral ammonium citrate, citric and formic acid) and particle size analysis. The classification of PR samples for direct

Ultrasonic testing of materials at level 2. Manual for the syllabi contained in IAEA-TECDOC-628, training guidelines in non-destructive testing techniques

International Nuclear Information System (INIS)

1999-01-01

The International Atomic Energy Agency (IAEA) has been active in the promotion of non-destructive testing (NDT) technology for many years. The prime reason for this interest has been the need for stringent quality control standards for the safe operation of nuclear installations. The IAEA has successfully executed a number of regional projects of which NDT was an important part. These were the Regional Co-operative Arrangements for the Promotion of Nuclear Science and Technology in Latin America (ARCAL), the Regional Co-operative Agreement for Asia and the Pacific (RCA), the African Regional Co-operative Agreement (AFRA) and lately the NDT Regional Project in West Asia. Through these projects a large number of persons have been trained in Member States and a state of self-sufficiency in this area of technology has been achieved in many of them. There has long been a realization of the need to have well established training guidelines and related books in order, firstly, to guide IAEA experts who were involved in this training programme and, secondly, to achieve some level of international uniformity and harmonization of training materials and consequent competence of personnel. The syllabi for training courses have been published in the form of two publications, IAEA-TECDOC-407 and IAEA-TECDOC-628. IAEA-TECDOC-628, as well as most of the international standards on the subject of training and certification of NDT personnel includes ISO 9712. The next logical step is to compile the textbooks and training manuals. Work in this regard has been undertaken and a manual on radiographic testing was issued in 1992 in the Training Course Series. This publication is a continuation of that effort. Earlier training notes on this subject existed in the form of IAEA-TECDOC-462, which was compiled in accordance with the syllabus of IAEA-TECDOC-407. These fulfilled the training needs of the member countries of RCA for quite some time. The present book is in fact an expanded and

The future use of pathway analysis in IAEA safeguards

International Nuclear Information System (INIS)

Budlong Sylvester, Kory; Pilat, J.; Murphy, Chantell

2013-01-01

Pathway analysis has the potential to play an important role in the development of a safeguards system that is more information driven, leveraging all the information available to the International Atomic Energy Agency (IAEA). Pathway analysis should be seen as an extension of traditional hypothesis testing used by the Agency in the past. The most attractive pathways based on the assessed capabilities of a given state can be identified and used in the development of state-level safeguards approaches. This ranking of pathways can be revised based on evidence of pathway use, or preparations for use, allowing limited safeguards resources to flow to the areas of highest concern. The possible uses of pathway analysis in the implementation of the IAEA's state-level concept are described along with implementation issues that will likely arise. The paper is followed by the slides of the presentation. (authors)

Clarifying the role of the IAEA

International Nuclear Information System (INIS)

Smith, R.

1983-01-01

The IAEA has many roles in promoting the role of nuclear energy for peaceful purposes. The most significant role that the IAEA undertakes is the development and application of safeguards to nuclear material, other material, equipment and facilities; this work consumes about 35% of the IAEA budget. The authority, procedures and limitations for the application of safeguards were described together with the relationship between the IAEA and the States where safeguards are in effect. Claims that the IAEA is not adequately fulfilling its safeguard role are usually based on misunderstandings of its role and authority. The IAEA's relationship to inspected States is not adversarial, regulatory, or guarding. It provides assurance to all States that peaceful nuclear activities are not diverted to a military program and in so doing enhances the reputation of States to whom safeguards are applied. Safeguards would be only one of many factors that would be involved in a States embarking on a military nuclear program. If proliferation of nuclear weapons occurs, this may be due in entirety or in part to these other factors. Many States could now undertake a military program but do not do so, because of their enlightened viewpoint that such activities are not in their own, or the world's best interests. However, any trend to further proliferation of nuclear weapons could be diminished by: -a lessening of political and economic tension between States, -restrictions on the supply of required technology, equipment, and material, and -an effective IAEA safeguard regime. There has been a regrettable trend to politicization in the direction and operation of the IAEA. It is hoped that this trend will be reversed and that IAEA will return to its earlier more technical role. There is a pressing need for the general public and governments to more fully understand the IAEA's role and its limitations

Safeguards agreement and additional protocol - IAEA instruments for control of nuclear materials distribution and their application in Tajikistan

International Nuclear Information System (INIS)

Nasrulloev, Kh.; Mirsaidov, U.

2010-01-01

Full text: It is known that IAEA plays an important role in facilitation of nuclear non-proliferation as international authority which carries out nuclear inspections. Republic of Tajikistan in 1997 signed nuclear weapon non-proliferation treaty. Then in 2004 Safeguards agreement, additional protocol and small quantity protocol were signed. During 5 years Republic of Tajikistan submits information on its nuclear activity as declarations, foreseen in article 2.3 of Additional protocol to Safeguards agreement. Currently 66 declarations are submitted. Information required in accordance with Safeguards agreement and Additional Protocol is figured on that IAEA could compile more detailed and exact conception about nuclear activity in Tajikistan and it has the following purpose: information will lead to more transparency, and make it possible to IAEA to ensure with high extent of confidence that in the framework of declared program, any unstated nuclear activity is concealed; the more exact and comprehensive information, the rare is questions and discrepancies are originating; required information is the basis for effective planning and IAEA activity realization, related not only with safeguards implementation in regard to declared nuclear material but also ensuring of confidence in absence of undeclared nuclear activity in Tajikistan. IAEA inspection mission consisting of Messrs. N.Lazarev and F. Coillou visited Dushanbe in 2008 for verification of republic’s declarations on account for and control of nuclear materials under Additional protocol and Small quantity protocol, as well as consultations were provided on correct declaration completing and providing information on all nuclear materials. Besides, in 2006, the training course was conducted in Chkalovsk with participation of Commonwealth of Independent States countries on Safeguards agreement and Additional protocol. These visits and events will facilitate to strengthening of weapons of mass destruction non

Directory of IAEA databases. 4. ed.

International Nuclear Information System (INIS)

1997-06-01

This fourth edition of the Directory of IAEA Databases has been prepared within the Division of NESI. ITs main objective is to describe the computerized information sources available to the public. This directory contains all publicly available databases which are produced at the IAEA. This includes databases stored on the mainframe, LAN servers and user PCs. All IAEA Division Directors have been requested to register the existence of their databases with NESI. At the data of printing, some of the information in the directory will be already obsolete. For the most up-to-date information please see the IAEA's World Wide Web site at URL: http:/www.iaea.or.at/databases/dbdir/. Refs, figs, tabs

Reference dosimeter system of the IAEA

International Nuclear Information System (INIS)

Mehta, Kishor; Girzikowsky, Reinhard

1995-01-01

Quality assurance programmes must be in operation at radiation facilities to satisfy national and international Standards. Since dosimetry has a vital function in these QA programmes, it is imperative that the dosimetry systems in use at these facilities are well calibrated with a traceability to a Primary Standard Dosimetry Laboratory. As a service to the Member States, the International Atomic Energy Agency operates the International Dose Assurance Service (IDAS) to assist in this process. The transfer standard dosimetry system that is used for this service is based on ESR spectrometry. The paper describes the activities undertaken at the IAEA Dosimetry Laboratory to establish the QA programme for its reference dosimetry system. There are four key elements of such a programme: quality assurance manual; calibration that is traceable to a Primary Standard Dosimetry Laboratory; a clear and detailed statement of uncertainty in the dose measurement; and, periodic quality audit. (Author)

Reference dosimeter system of the iaea

Science.gov (United States)

Mehta, Kishor; Girzikowsky, Reinhard

1995-09-01

Quality assurance programmes must be in operation at radiation processing facilities to satisfy national and international Standards. Since dosimetry has a vital function in these QA programmes, it is imperative that the dosimetry systems in use at these facilities are well calibrated with a traceability to a Primary Standard Dosimetry Laboratory. As a service to the Member States, the International Atomic Energy Agency operates the International Dose Assurance Service (IDAS) to assist in this process. The transfer standard dosimetry system that is used for this service is based on ESR spectrometry. The paper describes the activities undertaken at the IAEA Dosimetry Laboratory to establish the QA programme for its reference dosimetry system. There are four key elements of such a programme: quality assurance manual; calibration that is traceable to a Primary Standard Dosimetry Laboratory; a clear and detailed statement of uncertainty in the dose measurement; and, periodic quality audit.

Reference dosimeter system of the IAEA

International Nuclear Information System (INIS)

Mehta, K.; Girzikowsky, R.

1995-01-01

Quality assurance programmes must be in operation at radiation processing facilities to satisfy national and international standards. Since dosimetry has a vital function in these QA programmes, it is imperative that the dosimetry systems in use at these facilities are well calibrated with a traceability to a Primary Standard Dosimetry Laboratory. As a service to the Member States, the International Atomic Energy Agency operates the International Dose Assurance Service (IDAS) to assist in this process. The transfer standard dosimetry system that is used for this service is based on ESR spectrometry. The paper describes the activities undertaken at the IAEA Dosimetry Laboratory to establish the QA programme for its reference dosimetry system. There are four key elements of such a programme: quality assurance manual; calibration that is traceable to a Primary Standard Dosimetry Laboratory; a clear and detailed statement of uncertainty in the dose measurement; and, periodic quality audit. (author)

IAEA Concludes Safety Review at Gravelines Nuclear Power Plant, France

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA-led international team of nuclear safety experts noted a series of good practices and made recommendations to reinforce some safety measures during a review of operational safety at France's Gravelines Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 12 November 2012, focused on aspects essential to the safe operation of the NPP. The team was composed of experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain, Ukraine and the IAEA. The review covered the areas of management, organization and administration; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their possible use elsewhere. Examples include the following: - The Power Plant uses a staff-skills mapping process that significantly enhances knowledge of the facility's collective and individual skills and provides proactive management to address the loss of such skills; - As a measure to reduce the risk of workers' radiation exposure, the Power Plant uses a system to ensure that dose rate measurements are carried out at a precise distance from the source of radiation; and - Flood protection of the Power Plant is supported by special technical guidance documents and associated arrangements. The team identified a number of proposals for improvements to operational safety at Gravelines NPP. Examples include the following: - The Power Plant should reinforce its measures to prevent foreign objects from entering plant systems; - The Power Plant should ensure the 24-hour presence of an operator

Promoting safety in nuclear installations. The IAEA has established safety standards for nuclear reactors and provides expert review and safety services to assist Member States in their application

International Nuclear Information System (INIS)

2002-01-01

More than 430 nuclear power plants (NPPs) are currently operating in 30 countries around the world. The nuclear share of total electricity production ranges from about 20 percent in the Czech Republic and United States to nearly 78 percent in France and Lithuania. Worldwide, nuclear power generates about 16% of the total electricity. The safety of such nuclear installations is fundamental. Every aspect of a power plant must be closely supervised and scrutinized by national regulatory bodies to ensure safety at every phase. These aspects include design, construction, commissioning, trial operation, commercial operation, repair and maintenance, plant upgrades, radiation doses to workers, radioactive waste management and, ultimately, plant decommissioning. Safety fundamentals comprise defence-in-depth, which means having in place multiple levels of protection. nuclear facilities; regulatory responsibility; communicating with the public; adoption of the international convention on nuclear safety including implementation of IAEA nuclear safety standards. This publication covers topics of designing for safety (including safety concepts, design principles, and human factors); operating safety (including safety culture and advance in operational safety); risk assessment and management

Energy and nuclear power planning using the IAEA`s ENPEP computer package. Proceedings of a workshop

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

The Regional (Europe) Technical Co-operation Project on the Study of Energy Options Using the IAEA Planning Methodologies was first implemented by the IAEA in 1995. The project aims at improving national capabilities for energy, electricity and nuclear power planning and promoting regional co-operation among participating countries in the European region. The project includes the organization of workshops, training activities at the regional and national levels, scientific visits, etc. The proceedings of a workshop held in Warsaw, Poland, from 4 to 8 September 1995 are contained herein. The workshop had as a basic objective the analysis of the specific problems encountered by the represented countries during application of the IAEA`s ENPEP package in the conduct of national studies and to provide a forum for further co-operation among participating countries. A second objective of the workshop was to make proposals for future activities to be organized within the project. This publication is intended to serve as reference for the users of the IAEA`s ENPEP package, as well as for energy and electricity planners in general. Refs, figs, tabs.

A study to analyze IAEA planning of 2004-2005 programme and to establish cooperation directions with the IAEA

Energy Technology Data Exchange (ETDEWEB)

Oh, K. B.; Lee, K. S.; Lee, B. W.; Ko, H. S.; Ryu, J. S.; Lee, T. J.; Kim, M. R

2003-07-01

The objective of this study is to utilize the IAEA effectively through reflecting Korea's opinion fully for the planning of the Agency's 2004{approx}2005 Programme. This study first analyzed the current status of the IAEA Programme and Budget and reviewed the issues relevant to Korea. Second, this study assessed the IAEA 2004{approx}2005 Programme and drew up Korea's opinion for it. The official document including the opinions was submitted to the Secretariat. In reviewing the Programme, this study considered the strengths of Korea related to the Programme. Also some projects and CRPs, which can be lead by Korea, were proposed. The IAEA 2004{approx}2005 Programme reflected well the technical and social changes and its structure seems to be proper. The budget was proposed to be increased over 10%, violating the zero-real growth principle. This seems to be inevitable considering the increase of safeguards activities. However, there should be prepared some measures to avoid rapid increase of the burdens of the Member States. In the process of the planning of the IAEA 2004{approx}2005 Programme, the following points should be emphasized. First, SMR activities should be given a high priority considering the high interests of developing countries and be set up as a separate project as in the 2002{approx}2003 Programme. Second, more budget should be allocated for Project A.4.04(Support for demonstration of nuclear seawater desalination), considering the highest priority of the project in Program A. Third, it's better to change the title of Subprogram C.3 to 'Nuclear knowledge Preservation' to stick to the original rationale of the subprogram. There is a need for further activities such as establishing and implementing the concept of international nuclear school based on the result of the feasibility study done in 2002{approx}2003. Fourth, further activities needs to be added to the Project D.2.03 for the efficient conversion to high density

IAEA nuclear databases for applications

International Nuclear Information System (INIS)

Schwerer, Otto

2003-01-01

The Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA) provides nuclear data services to scientists on a worldwide scale with particular emphasis on developing countries. More than 100 data libraries are made available cost-free by Internet, CD-ROM and other media. These databases are used for practically all areas of nuclear applications as well as basic research. An overview is given of the most important nuclear reaction and nuclear structure databases, such as EXFOR, CINDA, ENDF, NSR, ENSDF, NUDAT, and of selected special purpose libraries such as FENDL, RIPL, RNAL, the IAEA Photonuclear Data Library, and the IAEA charged-particle cross section database for medical radioisotope production. The NDS also coordinates two international nuclear data centre networks and is involved in data development activities (to create new or improve existing data libraries when the available data are inadequate) and in technology transfer to developing countries, e.g. through the installation and support of the mirror web site of the IAEA Nuclear Data Services at IPEN (operational since March 2000) and by organizing nuclear-data related workshops. By encouraging their participation in IAEA Co-ordinated Research Projects and also by compiling their experimental results in databases such as EXFOR, the NDS helps to make developing countries' contributions to nuclear science visible and conveniently available. The web address of the IAEA Nuclear Data Services is http://www.nds.iaea.org and the NDS mirror service at IPEN (Brasil) can be accessed at http://www.nds.ipen.br/ (author)

IAEA Orientation for Diplomats 2013. The IAEA in Overview

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-02-15

The IAEA's mission is to prevent the spread of nuclear weapons and to help all countries - especially in the developing world - benefit from the peaceful, safe and secure use of nuclear science and technology. Since the Agency was founded in 1957, our work has constantly evolved to meet the changing needs of our member states. We work to improve human and animal health. We help farmers to grow more abundant and robust crops. We help to make clean water more available and to combat environmental pollution. We help countries which wish to use nuclear power to do so safely and securely. Through all of these activities, the IAEA helps member states to use nuclear technology to meet the basic needs of their people. Nuclear power is the best-known peaceful application of nuclear energy. The fukushima Daiichi accident in Japan in 2011 caused considerable public anxiety throughout the world and damaged confidence in nuclear power. Nevertheless, use of nuclear power looks set to grow steadily in the next 20 years, although at a slower rate than was expected before the accident. The fukushima Daiichi accident led to a renewed focus on safety. In 2011, IAEA member states agreed an Action Plan on nuclear safety which they, and the Agency, are now implementing. The Agency also serves as the global platform for strengthening nuclear security. Our work focuses on helping to minimize the risk of nuclear and other radioactive material falling into the hands of terrorists, or of nuclear facilities being subjected to malicious acts. The IAEA is the only organization within the UN system with expertise in nuclear technologies. Our unique specialist laboratories help transfer knowledge and expertise to our member states in areas such as human health, food, water and the environment. cancer control in developing countries is a major priority for the Agency and for me personally. Hundreds of thousands of patients in developing countries do not have access to treatment that could save

IAEA Orientation for Diplomats 2013. The IAEA in Overview

International Nuclear Information System (INIS)

2013-02-01

The IAEA's mission is to prevent the spread of nuclear weapons and to help all countries - especially in the developing world - benefit from the peaceful, safe and secure use of nuclear science and technology. Since the Agency was founded in 1957, our work has constantly evolved to meet the changing needs of our member states. We work to improve human and animal health. We help farmers to grow more abundant and robust crops. We help to make clean water more available and to combat environmental pollution. We help countries which wish to use nuclear power to do so safely and securely. Through all of these activities, the IAEA helps member states to use nuclear technology to meet the basic needs of their people. Nuclear power is the best-known peaceful application of nuclear energy. The fukushima Daiichi accident in Japan in 2011 caused considerable public anxiety throughout the world and damaged confidence in nuclear power. Nevertheless, use of nuclear power looks set to grow steadily in the next 20 years, although at a slower rate than was expected before the accident. The fukushima Daiichi accident led to a renewed focus on safety. In 2011, IAEA member states agreed an Action Plan on nuclear safety which they, and the Agency, are now implementing. The Agency also serves as the global platform for strengthening nuclear security. Our work focuses on helping to minimize the risk of nuclear and other radioactive material falling into the hands of terrorists, or of nuclear facilities being subjected to malicious acts. The IAEA is the only organization within the UN system with expertise in nuclear technologies. Our unique specialist laboratories help transfer knowledge and expertise to our member states in areas such as human health, food, water and the environment. cancer control in developing countries is a major priority for the Agency and for me personally. Hundreds of thousands of patients in developing countries do not have access to treatment that could save

Basic Safety Standards for Radiation Protection - 1967 Edition

International Nuclear Information System (INIS)

1967-01-01

This first revision of the Basic Safety Standards was approved by the IAEA Board of Governors in September 1965. It was prepared with the assistance of a panel of experts chaired by Prof. L. Bugnard, Director of the French Institut National d'Hygiene, and attended by representatives of several international organizations. Comments from Member States were considered and changes were introduced on the basis of recommendations made by the International Commission on Radiological Protection in 1966. The Director General of the IAEA has been authorized by the Board to apply the revised Standards to IAEA and IAEA-assisted operations. It has also been recommended that the national regulations of Member States should conform, as far as is practicable, to the revised Standards. (author)

IAEA Completes Nuclear Security Review Mission in United States

International Nuclear Information System (INIS)

2013-01-01

Full text: A team of nuclear security experts led by the International Atomic Energy Agency (IAEA) today completed a mission to review nuclear security practices of civil nuclear facilities licensed by the United States Nuclear Regulatory Commission (NRC). Conducted at the U.S. Government's request, the two-week International Physical Protection Advisory Service (IPPAS) mission reviewed the United States' nuclear security-related legislative and regulatory framework. As part of this work, the IPPAS team, led by John O'Dacre of Canada and comprising nine experts from eight IAEA Member States, met with NRC officials and reviewed the physical protection systems at the Center for Neutron Research (NCNR) at the National Institute of Standards and Technology. The IPPAS team concluded that nuclear security within the U.S. civil nuclear sector is robust and sustainable and has been significantly enhanced in recent years. The team identified a number of good practices in the nation's nuclear security regime and at the NCNR. The IPPAS team also made a recommendation and some suggestions for the continuing improvement of nuclear security overall. The mission in the United States was the 60th IPPAS mission organized by the IAEA. 'Independent international peer reviews such as IAEA IPPAS missions are increasingly being recognized for their value as a key component for exchanges of views and advice on nuclear security measures', said Khammar Mrabit, Director of the IAEA Office of Nuclear Security. 'The good practices identified during this mission will contribute to the continuous improvements of nuclear security in other Member States'. The IPPAS team provided a draft report to the NRC and will submit a final report soon. Because it contains security-related information about a specific nuclear site, IPPAS reports are not made public. 'The IPPAS programme gives us a chance to learn from the experience and perspective of our international partners', said NRC Chairman Allison M

IAEA's Safeguards Implementation Practices Guides

International Nuclear Information System (INIS)

Mathews, C.; Sahar, S.; Cisar, V.

2015-01-01

Implementation of IAEA safeguards benefits greatly from effective cooperation among the IAEA, State or regional authorities (SRAs), and operators of facilities and other locations. To improve such cooperation, the IAEA has produced numerous safeguards guidance documents in its Services Series publications. The IAEA also provides assistance, training and advisory services that are based on the published guidance. The foundation of the IAEA's safeguards guidance is the Guidance for States Implementing Comprehensive Safeguards Agreements and Additional Protocols (IAEA Services Series 21) published in March of 2012. The large majority of States have concluded CSAs and therefore will benefit from this guidance. Many States with CSAs also have concluded small quantities protocols (SQPs) to their CSAs. In April of 2013, the IAEA published the Safeguards Implementation Guide for States with SQPs (IAEA Services Series 22). Other guidance focuses on specific topics such as preparing additional protocol declarations and nuclear material accounting. This paper will describe a recent effort to produce a ''Safeguards Implementation Practices'' (SIP) series of guides that will provide additional explanatory information about safeguards implementation, and share the practical experiences and lessons learned of States and the IAEA over the many decades of implementing safeguards. The topics to be addressed in four SIP guides include: 1) Facilitating IAEA Verification Activities; 2) Establishing and Maintaining State Safeguards Infrastructure; 3) Provision of Information to the IAEA; and 4) Collaborative Approaches to Safeguards Implementation. The SIP Guides build upon the content of IAEA Services Series 21. Because the SIP Guides are intended to share implementation practices and lessons learned of States, a number of experienced State experts have participated in the development of the documents, through a joint Member State Support Programme task

Existing and future international standards for the safety of radioactive waste disposal

International Nuclear Information System (INIS)

Linsley, G.

1999-01-01

In this paper the essential features of the current international safety standards are summarised and the issues being raised for inclusion in future standards are discussed. The safety standards of the IAEA are used as the basis for the review and discussion. The IAEA has established a process for establishing international standards of safety for radioactive waste management through its Radioactive Waste Safety Standards (RADWASS) programme. The RADWASS documents are approved by a comprehensive process involving regulatory and other experts from all concerned IAEA Member States. A system of committees for approving the IAEAs safety standards has been established. For radioactive waste safety the committee for review and approval is the Waste Safety Standards Advisory Committee (WASSAC). In 1995 the IAEA published 'The Principles of Radioactive Waste Management' as the top level document in the RADWASS programme. The report sets out the basis principles which most experts believe are fundamental to the safe management of radioactive wastes

Supervision of nuclear safety - IAEA requirements, accepted solutions, trends

International Nuclear Information System (INIS)

Jurkowski, M.

2007-01-01

Ten principles of the nuclear safety, based on the IAEA's standards are presented. Convention on Nuclear Safety recommends for nuclear safety landscape, the control transparency, culture safety, legal framework and knowledge preservation. Examples of solutions accepted in France, Finland, and Czech Republic are discussed. New trends in safety fundamentals and Integration Regulatory Review are presented

Analysis of uncertainties in the IAEA/WHO TLD postal dose audit system

Energy Technology Data Exchange (ETDEWEB)

Izewska, J. [Department of Nuclear Sciences and Applications, International Atomic Energy Agency, Wagramer Strasse 5, Vienna (Austria)], E-mail: j.izewska@iaea.org; Hultqvist, M. [Department of Medical Radiation Physics, Karolinska Institute, Stockholm University, Stockholm (Sweden); Bera, P. [Department of Nuclear Sciences and Applications, International Atomic Energy Agency, Wagramer Strasse 5, Vienna (Austria)

2008-02-15

The International Atomic Energy Agency (IAEA) and the World Health Organisation (WHO) operate the IAEA/WHO TLD postal dose audit programme. Thermoluminescence dosimeters (TLDs) are used as transfer devices in this programme. In the present work the uncertainties in the dose determination from TLD measurements have been evaluated. The analysis of uncertainties comprises uncertainties in the calibration coefficient of the TLD system and uncertainties in factors correcting for dose response non-linearity, fading of TL signal, energy response and influence of TLD holder. The individual uncertainties have been combined to estimate the total uncertainty in the dose evaluated from TLD measurements. The combined relative standard uncertainty in the dose determined from TLD measurements has been estimated to be 1.2% for irradiations with Co-60 {gamma}-rays and 1.6% for irradiations with high-energy X-rays. Results from irradiations by the Bureau international des poids et mesures (BIPM), Primary Standard Dosimetry Laboratories (PSDLs) and Secondary Standards Dosimetry Laboratories (SSDLs) compare favourably with the estimated uncertainties, whereas TLD results of radiotherapy centres show higher standard deviations than those derived theoretically.

IAEA Guidance for Safeguards Implementation in Facility Design and Construction

International Nuclear Information System (INIS)

Sprinkle, J.; Hamilton, A.; Poirier, S.; Catton, A.; Ciuculescu, C.; Ingegneri, M.; Plenteda, R.

2015-01-01

One of the IAEA's statutory objectives is to seek to accelerate and enlarge the contribution of nuclear energy to peace, health and prosperity throughout the world. One way the IAEA works to achieve this objective is through the publication of technical series that can provide guidance to Member States. These series include the IAEA Services Series, the IAEA Safety Standard Series, the IAEA Nuclear Security Series and the IAEA Nuclear Energy Series. The Nuclear Energy Series is comprised of publications designed to encourage and assist research and development on, and practical application of, nuclear energy for peaceful purposes. This includes guidance to be used by owners and operators of utilities, academia, vendors and government officials. The IAEA has chosen the Nuclear Energy Series to publish guidance for States regarding the consideration of safeguards in nuclear facility design and construction. Historically, safeguards were often applied after a facility was designed or maybe even after it was built. However, many in the design and construction community would prefer to include consideration of these requirements from the conceptual design phase in order to reduce the need for retro-fits and modifications. One can then also take advantage of possible synergies between safeguards, security, safety and environmental protection and reduce the project risk against cost increments and schedule slippage. The IAEA is responding to this interest with a suite of publications in the IAEA Nuclear Energy Series, developed with the assistance of a number of Member State Support Programmes through a joint support programme task: · International Safeguards in Nuclear Facility Design and Construction (NP-T-2.8, 2013), · International Safeguards in the Design of Nuclear Reactors (NP-T-2.9, 2014), · International Safeguards in the Design of Spent Fuel Management (NF-T-3.1, tbd), · International Safeguards in the Design of Fuel Fabrication Plants (NF-T-4.7, tbd

IAEA Director General to Visit Iran

International Nuclear Information System (INIS)

2013-01-01

Full text: IAEA Director General Yukiya Amano will travel to Tehran on 10 November 2013 to meet senior Iranian leaders on Monday, 11 November 2013, with the aim of strengthening dialogue and cooperation. Separately, as previously announced, IAEA and Iranian experts will meet in Tehran on Monday to discuss technical issues. IAEA)

The trends of NDT technologies - IAEA experience

International Nuclear Information System (INIS)

Khan, A. A.; Einav, I.

2003-01-01

Non destructive testing (NDT) is an essential technology for quality control leading to more reliable and safer industrial as well as nuclear plants. This was the main reason for the IAEA to undertake the promotion of this technology in the world. Through its regional and technical assistance programmes the NDT technology programmes encompass approximately more than 80 developing countries. The main focus of the NDT programme has been the creation of core groups of personnel able to undertake education, training and certification of NDT personnel and provision of NDT services to industries, creation of national certifying bodies, issuance of national standards compatible with ISO 9712 and the establishment of Professional NDT Societies. The programme has met a great success in most of the Member States. The paper will review the programmes of the IAEA in the field of NDT and provide an assessment of the present status of NDT technology development both in the developing as well as developed countries. (Author)

IAEA safeguards for geological repositories

International Nuclear Information System (INIS)

Moran, B.W.

2005-01-01

In September. 1988, the IAEA held its first formal meeting on the safeguards requirements for the final disposal of spent fuel and nuclear material-bearing waste. The consensus recommendation of the 43 participants from 18 countries at this Advisory Group Meeting was that safeguards should not terminate of spent fuel even after emplacement in, and closure of, a geologic repository.' As a result of this recommendation, the IAEA initiated a series of consultants' meetings and the SAGOR Programme (Programme for the Development of Safeguards for the Final Disposal of Spent Fuel in Geologic Repositories) to develop an approach that would permit IAEA safeguards to verify the non-diversion of spent fuel from a geologic repository. At the end of this process, in December 1997, a second Advisory Group Meeting, endorsed the generic safeguards approach developed by the SAGOR Programme. Using the SAGOR Programme results and consultants' meeting recommendations, the IAEA Department of Safeguards issued a safeguards policy paper stating the requirements for IAEA safeguards at geologic repositories. Following approval of the safeguards policy and the generic safeguards approach, the Geologic Repository Safeguards Experts Group was established to make recommendations on implementing the safeguards approach. This experts' group is currently making recommendations to the IAEA regarding the safeguards activities to be conducted with respect to Finland's repository programme. (author)

Mass media and nuclear energy - IAEA's role

International Nuclear Information System (INIS)

Kyd, D.R.

1993-11-01

The presentation covers the following areas: the wide spectrum of media outlets that the IAEA seeks to serve and their differing needs; the resources available to the IAEA for that purpose; the way in which IAEA endeavours to disseminate authoritative, reliable nuclear-related information to media; the exceptional role the IAEA may be called on to play in emergency situations

IAEA activities on steam generator life management

International Nuclear Information System (INIS)

Gueorguiev, B.; Lyssakov, V.; Trampus, P.

2002-01-01

The International Atomic Energy Agency (IAEA) carries out a set of activities in the field of Nuclear Power Plant (NPP) life management. Main activities within this area are implemented through the Technical Working Group on Life Management of NPPs, and mostly concentrated on studies of understanding mechanisms of degradation and their monitoring, optimisation of maintenance management, economic aspects, proven practices of and approaches to plant life management including decommissioning. The paper covers two ongoing activities related to steam generator life management: the International Database on NPP Steam Generators and the Co-ordinated Research Project on Verification of WWER Steam Generator Tube Integrity (WWER is the Russian designed PWR). The lifetime assessment of main components relies on an ability to assess their condition and predict future degradation trends, which to a large extent is dependent on the availability of relevant data. Effective management of ageing and degradation processes requires a large amount of data. Several years ago the IAEA started to work on the International Database on NPP Life Management. This is a multi-module database consisting of modules such as reactor pressure vessels materials, piping, steam generators, and concrete structures. At present the work on pressure vessel materials, on piping as well as on steam generator is completed. The paper will present the concept and structure of the steam generator module of the database. In countries operating WWER NPPs, there are big differences in the eddy current inspection strategy and practice as well as in the approach to steam generator heat exchanger tube structural integrity assessment. Responding to the need for a co-ordinated research to compare eddy current testing results with destructive testing using pulled out tubes from WWER steam generators, the IAEA launched this project. The main objectives of the project are to summarise the operating experiences of WWER

General formulation of standard model the standard model is in need of new concepts

International Nuclear Information System (INIS)

Khodjaev, L.Sh.

2001-01-01

The phenomenological basis for formulation of the Standard Model has been reviewed. The Standard Model based on the fundamental postulates has been formulated. The concept of the fundamental symmetries has been introduced: To look for not fundamental particles but fundamental symmetries. By searching of more general theory it is natural to search first of all global symmetries and than to learn consequence connected with the localisation of this global symmetries like wise of the standard Model

Methodological Aspects of the IAEA State Level Concept and Acquisition Path Analysis: A State’s Nuclear Fuel Cycle, Related Capabilities, and the Quantification of Acquisition Paths

International Nuclear Information System (INIS)

Lance, K. Kim; Renda, Guido; Cojazzi, Giacomo G. M.

2015-01-01

Within its State Level Concept (SLC), the International Atomic Energy Agency (IAEA) envisions a State Level Approach (SLA) for safeguards implementation that considers, inter alia, a State’s nuclear and nuclear-related activities and capabilities as a whole when developing an annual implementation plan. Based on the assessed nuclear fuel cycle and related capabilities of a State, Acquisition Path Analysis (APA) identifies, characterizes, and prioritizes plausible routes for acquiring weapons-usable material to aid in safeguards implementation planning. A review of proposed APA methods and historical evidence indicates that assessments of pathway completion time can be fraught with uncertainty and subject to bias, potentially undermining safeguards effectiveness and efficiency. Based on considerations of theory and evidence, a number of methodological insights are identified to support consistent implementation and ongoing APA development. The use of algorithms to support APA and SLA processes in lieu of human judgement is a contentious issue requiring an evidence- based assessment and is also briefly discussed. This paper captures concepts derived primarily from open sources of information, including publications, presentations, and workshops on on-going APA development by the IAEA and various Member States Support Programs (MSSP) as well as relevant work found in the open literature. While implementation of the SLA has begun for a number of States, these SLAs are being updated and developed for other States. In light of these ongoing developments, the topics covered here should be considered a snapshot in time that does not reflect finished products and does not necessarily reflect official views.

Global nuclear developments and the IAEA Director General Mohamed ElBaradei reviews achievements, challenges at IAEA General Conference

International Nuclear Information System (INIS)

2000-01-01

In a statement to the 44th regular session of the Agency's General Conference (18 - 22 September 2000, Austria Center Vienna), the IAEA Director General reviewed nuclear developments from the IAEA perspectives. In this connection, the Director General signalled the IAEA's achievements and its readiness to provide its services as may be requested in response to global developments. He also underlined present and future challenges shaping the IAEA agenda, including financial challenges

21. IAEA fusion energy conference. Book of abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

Recognizing the prominent role that nuclear energy plays in the world, and based on the expectation that nuclear fusion will be able to provide an abundant source of energy, the International Atomic Energy Agency (IAEA) supports the exchange of scientific and technical information on fusion research through conferences, meetings and projects. The 21st IAEA Fusion Energy Conference (FEC 2006) provided a forum for presenting and discussing the progress that is being made in fusion experiments, theory and technological developments. It is expected that the progress in the establishment of ITER since the last Fusion Energy Conference will put more emphasis on the physics and technology R and D aspects in the realization of fusion as a clean and lasting energy source. FEC 2006 covered the following topics: OV Overviews; EX Magnetic Confinement Experiments; TH Magnetic Confinement Theory and Modelling; IT ITER Activities; IF Inertial Fusion Experiments and Theory; IC Innovative Concepts; FT Fusion Technology and Power Plant Design; SE Safety, Environmental and Economic Aspects of Fusion. At the same time, a series of satellite meetings and fusion related exhibitions took place.

The IAEA at work

International Nuclear Information System (INIS)

2004-03-01

Fifty years ago, Dwight Eisenhower stood before the United Nations to offer both a warning and a vision. The knowledge to build an atomic bomb was in the hands of rival powers and would soon be shared by many countries, the President said. It was time to create a U.N. body that could ensure that the new technology served no military purpose. It was time, moreover, to 'devise methods whereby this fissionable material would be allocated to serve the peaceful pursuits of mankind' in agriculture, medicine and other peaceful activities. Eisenhower foresaw a world safe from the destructive power of atomic fission but gaining from its technological advances. Half a century later, the world continues to witness his foresight through the work of the International Atomic Energy Agency (IAEA). The IAEA aims at four formidable goals: safeguarding nuclear nonproliferation; enhancing the security of nuclear facilities and radioactive materials; ensuring the safety of nuclear technologies; and promoting nuclear science to meet human needs. As the world's 'nuclear watchdog,' the IAEA's impartial inspectorate verifies the peaceful uses of nuclear energy in scores of countries. By joining the Agency's strengthened safeguards system and concluding an Additional Protocol, countries can assure the world-and the IAEA can verify-that their nuclear activities are not used for weapons purposes. True to Eisenhower's vision, the power of the atom is being tapped for many human benefits, especially in the world's less developed nations. Extreme poverty remains a profound problem today: some 1.2 billion people in the developing world survive marginally on less that US$1 per day. Another 2.8 billion struggle on less than US$2 per day. The IAEA is mobilizing nuclear science to help address these pressing needs. From managing water better, to controlling pests and diseases, to protecting the environment, the IAEA is helping poor countries make sizeable advances. At the same time, the IAEA works

IAEA coordinated research programme on heat transfer behavior and thermo-hydraulics code testing for super critical water cooled reactors

International Nuclear Information System (INIS)

Bilbao y Leon, Sama; Aksan, Nusret

2009-01-01

One of the key roles of the IAEA is to foster the collaboration among Member States on the development of advances in technology for advanced nuclear power plants. There is high international interest, both in developing and industrialized countries, in innovative supercritical water-cooled reactors (SCWRs), primarily because such concepts will achieve high thermal efficiencies (44-45%) and promise improved economic competitiveness utilizing and building upon the recent developments for highly efficient fossil power plants. The SCWR has been selected as one of the promising concepts for development by the Generation-IV International Forum. Following the advice of the IAEA Nuclear Energy Department's Technical Working Groups on Advanced Technologies for LWRs and HWRs (the TWG-LWR and TWG-HWR), with the feedback from the Gen-IV SCWR Steering Committee, and in coordination with the OECD-NEA, IAEA has recently started a Coordinated Research Programme (CRP) in the areas of heat transfer behaviour and testing of thermo-hydraulic computer methods for Supercritical Water-Cooled Reactors. The first Research Coordination Meeting (RCM) of the CRP was held at the IAEA Headquarters, in Vienna, Austria in July 2008. This paper summarizes the current status of the CRP, including the Integrated Research Plan and the general schedule for the CRP. (author)

Nuclear safety review 1992. Part D of the IAEA Yearbook 1992

International Nuclear Information System (INIS)

1992-09-01

Activities aimed at upgrading the safety of nuclear power plants in countries of eastern Europe, the birth of the concept of an international nuclear safety convention and the new recommendations of the International Commission on Radiological Protection (ICRP) made 1991 a very important year in the fields of radiation protection and nuclear safety. Following the political changes in eastern Europe, attention is now centred on the safety of Soviet designed reactors. It has become apparent that the safety approach adopted in the design and operation of the older reactors (WWER-440/230s) was different from that which has been prevalent in western countries for many years and does not meet present safety standards. In addition to continuing its project on the safety of WWER-440/230s, the IAEA is proceeding with activities relating to the other reactor types operating in eastern European countries: WWER-440/213s, WWER-l000s and RBMKs. Concern for nuclear safety led the decision makers participating in the International Conference on the Safety of Nuclear Power: Strategy for the Future to support the concept of an international nuclear safety convention - a concept later endorsed by the IAEA General Conference and Board of Governors, the latter authorizing the Director General to set up an open ended working group with the task of carrying out the necessary preparations for such a convention. The radiation protection area was dominated by work on the revision of regulations and standards in the light of the new ICRP recommendations. The revision of the Basic Safety Standards for Radiation Protection, which is well under way, reflects a major international consensus on the basic requirements for restricting the risks from practices which could expose people to radiation. Co-operation between interested international organizations through a Joint Secretariat has proved to be efficient. Major lessons can be learned from experience with the utilization of nuclear technology

The IAEA Activities in the Field of Fast Reactors Technology Development

International Nuclear Information System (INIS)

Monti, Stefano

2011-01-01

Main activities of the IAEA Programme on Fast Reactor: Carry out Collaborative Research Projects (CRPs) of common interest to the TWG-FR Member States in the field of FRs and ADS; Secure Training and Education in the field of fast neutron system physics, technology and applications; Support Fast Reactor data retrieval and knowledge preservation activities in MSs; Provide support to IAEA Nuclear Safety and Security Department for preparation of fast reactor Safety standards / requirements / guides. IAEA TWG-FR Functions: Provide advice and guidance, and marshal support in their countries for implementation of IAEA’s programmatic activities in the area of advanced technologies and R&D for fast reactors and sub-critical hybrid systems for energy production and for utilization/transmutation of long-lived nuclides; Provide a forum for information and knowledge sharing on national and international development programs; Act as a link between IAEA’s activities in the specific area of the TWG-FR and national scientific communities, delivering information from and to national communities

IAEA Operational Safety Team Reviews Cattenom Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has reviewed operational safety at France's Cattenom Nuclear Power Plant (NPP) noting a series of good practices as well as recommendations and suggestions to reinforce them. The IAEA assembled an international team of experts at the request of the Government of France to conduct an Operational Safety Review (OSART) of Cattenom NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review of the plant from 14 November to 1 December 2011. The team was made up of experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Japan, Russia, Slovakia, South Africa, Sweden, Ukraine, the United Kingdom and the IAEA. The team at Cattenom conducted an in-depth review of the aspects essential to the safe operation of the NPP, which is largely under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. Cattenom is the first plant in Europe to voluntarily undertake a Severe Accident Management review during an OSART review. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: Sheets are displayed in storage areas where combustible material is present - these sheets are updated readily and accurately by the area owner to ensure that the fire limits are complied with; A simple container is attached to the neutron source handling device to ensure ease and safety of operations and reduce possible radiation exposure during use

Approach to IAEA material-balance verification at the Portsmouth Gas Centrifuge Enrichment Plant

International Nuclear Information System (INIS)

Gordon, D.M.; Sanborn, J.B.; Younkin, J.M.; DeVito, V.J.

1983-01-01

This paper describes a potential approach by which the International Atomic Energy Agency (IAEA) might verify the nuclear-material balance at the Portsmouth Gas Centrifuge Enrichment Plant (GCEP). The strategy makes use of the attributes and variables measurement verification approach, whereby the IAEA would perform independent measurements on a randomly selected subset of the items comprising the U-235 flows and inventories at the plant. In addition, the MUF-D statistic is used as the test statistic for the detection of diversion. The paper includes descriptions of the potential verification activities, as well as calculations of: (1) attributes and variables sample sizes for the various strata, (2) standard deviations of the relevant test statistics, and (3) the detection sensitivity which the IAEA might achieve by this verification strategy at GCEP

New IAEA guidelines on environmental remediation

Energy Technology Data Exchange (ETDEWEB)

Fesenko, Sergey [International Atomic Energy Agency, A2444, Seibersdorf (Austria); Howard, Brenda [Centre for Ecology and Hydrology, Lancaster Environment Centre, LA1 4AP, Lancaster (United Kingdom); Kashparov, Valery [Ukrainian Institute of Agricultural Radiology, 08162, 7, Mashinobudivnykiv str., Chabany, Kyivo-Svyatoshin region, Kyiv (Ukraine); Sanzharova, Natalie [Russian Institute of Agricultural Radiology and Agroecology, Russian Federation, 249032, Obninsk (Russian Federation); Vidal, Miquel [Analytical Chemistry Department-Universitat de Barcelona, Barcelona, 08028 Barcelona (Spain)

2014-07-01

In response to the needs of its Member States, the International Atomic Energy Agency (IAEA) has published many documents covering different aspects of remediation of contaminated environments. These documents range from safety fundamentals and safety requirements to technical documents describing remedial technologies. Almost all the documents on environmental remediation are related to uranium mining areas and decommissioning of nuclear facilities. IAEA radiation safety standards on remediation of contaminated environments are largely based on these two types of remediation. The exception is a document related to accidents, namely the IAEA TRS No. 363 'Guidelines for Agricultural Countermeasures Following an Accidental Release of Radionuclides'. Since the publication of TRS 363, there has been a considerable increase in relevant information. In response, the IAEA initiated the development of a new document, which incorporated new knowledge obtained during last 20 years, lessons learned and subsequent changes in the regulatory framework. The new document covers all aspects related to the environmental remediation from site characterisation to a description of individual remedial actions and decision making frameworks, covering urban, agricultural, forest and freshwater environments. Decisions taken to commence remediation need to be based on an accurate assessment of the amount and extent of contamination in relevant environmental compartments and how they vary with time. Major aspects of site characterisation intended for remediation are described together with recommendations on effective sampling programmes and data compilation for decision making. Approaches for evaluation of remedial actions are given in the document alongside the factors and processes which affect their implementation for different environments. Lessons learned following severe radiation accidents indicate that remediation should be considered with respect to many different

Programmatic activities of IAEA in nuclear medicine

International Nuclear Information System (INIS)

Padhy, A.K.

2004-01-01

Nuclear medicine is high-tech medicine. Nevertheless, it is essential for addressing important health problems of people living in developing countries also. Not only is it sometimes expensive to start with, it also involves a lot of technical know-how, requiring transfer of technology from developed to the developing countries. The rapid development of nuclear medicine, of sophisticated instrumentation and radiopharmaceuticals has resulted in an enormous increase in costs and in the need for maintaining quality. These constitute a challenge and a venture when promoting nuclear medicine globally and particularly in developing countries. No other international organization except IAEA has any specific mandate for application of nuclear energy in the area of human health. WHO has no specific programin nuclear medicine, hence the importance of IAEA's involvement. The IAEA has, ever since its inception, given high priority to enhancing the awareness and capabilities of developing member states to employ nuclear technology for health care and medical research. Much of the Agency promoted research in nuclear medicine is delivered through the so called co-ordinated research projects (CRPs). The CRPs are normally organised as multi-center, prospective studies so that large volume of scientific data could be generated in a short period of 18-24 months. The research is normally done within an operational frame work, established and co-ordinated by the IAEA. The reason for this is that the results can be compared despite site or country specific differences. The methods and materials used for such studies usually conform to a predetermined standard. The protocols for various investigations, criteria for patient selection, mode of arriving at a final diagnosis and analysis of data from these multi-center studies are normally agreed upon by the Chief Scientific Investigators from each participating institution and the IAEA prior to the start of the actual work programme. The

Nuclear information: An overview of IAEA's activities

International Nuclear Information System (INIS)

Marchesi, I.H.; Konstantinov, L.V.

1986-01-01

As stated in this overview of IAEA nuclear information activities the Agency's role in information services is rapidly evolving and multifaceted. The Agency maintains more than 200 computerized files of information. Some 60 of these are part of systems directly related to nuclear activities. Some of these are briefly profiled in this overview such as INIS, the IAEA Nuclear Data Programme, the IAEA Incident Reporting System, the IAEA Energy and Economic Databank, the IAEA Power Reactor Information System, the Nuclear Fuel Cycle Information System, and the International Uranium Geology Information System. Future directions are pointed out. Different ways to upgrade information systems are listed

Thermohydraulic analysis of the IAEA standard problem test on the PMK-NHV facility; Termohidraulicna analiza standardnega problem MAAE na poskusni napravi PMK-NHV

Energy Technology Data Exchange (ETDEWEB)

Stritar, A [Institut Jozef Stefan, Ljubljana (Yugoslavia)

1987-07-01

International Atomic Energy Agency (IAEA) has supported a standard test problem simulating small break loss of coolant accident on the test facility PMH-NHV in Budapest. The present pretest analysis of that transient was done using the computer code RELAP4/MOD6. The results were compared to the measurements data and to data of 19 other laboratories around the world that have performed the same analysis. The correspondence of the results to the measured data is reasonable. There are bigger discrepancies, which in turn influence other variables. (author)

Certified Reference Material IAEA-448: Soil from Oil Field Contaminated with Technically Enhanced Radium-226

International Nuclear Information System (INIS)

2013-01-01

To ensure reliable evaluation of potential radiological hazards and proper decision making related to radiation protection measures, the IAEA, through the IAEA Environment Laboratories, supports Member State laboratories in their efforts to maintain readiness and to improve the quality of analytical results. It does so by producing reference materials, by developing standardized methods for sample collection and analysis, and by conducting interlaboratory comparisons and proficiency tests as tools for external quality control of analytical results. The problem of naturally occurring radioactive material (NORM) contamination is known to be widespread, occurring in oil and gas production facilities throughout the world. It has become a subject of attention in many IAEA Member States. In response to this radiological concern, facilities in many Member States have been characterizing the nature and extent of NORM in oil and gas installations and in the surrounding environment, evaluating the potential for exposure to workers and the public, and developing methods for properly managing these relatively high massic activity residues. Within this context, the IAEA Environment Laboratories, in cooperation with the Atomic Energy Commission of Syria, an IAEA Collaborating Centre, have prepared a new certified reference material of soil contaminated with NORM, identified as IAEA-448, certified for the massic activity of 226Ra. This report presents the methodologies used for the production and certification of IAEA-448

Report on the intercomparison run IAEA-155 trace elements in whey powder

International Nuclear Information System (INIS)

Zeiller, E.; Strachnov, V.; Dekner, R.

1990-11-01

Analytical results need to be reliable, and analysts are well serviced to test their complete analytical systems, methods, instruments, personnel, data reduction, etc., on a frequent basis. Besides the use of standard reference materials, the intercomparison runs provide an excellent opportunity for the determination of accuracy. By comparing their results with results obtained by different methods of preparation and measurement, the participating laboratories have the opportunity to check their analytical performances. At the same time the IAEA's AQCS can establish the concentration of some elements for certification purposes. The participants were requested to determine as many elements as possible with emphasis on ''essential'' and ''toxic'' elements related to human health and environmental pollution in the intercomparison whey powder sample (IAEA-155) as well as in the control sample IAEA. It was expected that the results for IAEA would improve the evaluation of the intercomparison results of IAEA-155 as the concentrations of some inorganic constituents were well established in the IAEA sample. In total 69 laboratories from 24 different countries participated in this exercise. As a basis for the evaluation, 580 laboratory means were reported comprising 2699 individual results for 45 elements. For 3 additional elements information was supplied that the value was below the detection limits of the methods. Even though information and data on 48 elements were reported for IAEA-155 only 4 elements are assigned Class A and 13 elements Class B recommended values. The elements Mg, Mn, Na and P were assigned ''Class A''. But contrary to some former intercomparison exercises, this time sufficient results could be obtained to set ''Class B'' recommended values for some ''difficult to determine'' elements like Cd, Co, Cr, Hg, Ni, Pb, Se. Figs, 45 tabs

IAEA Technical Cooperation and the NPT

International Nuclear Information System (INIS)

Barretto, Paulo M.C.; Cetto, Ana Maria

2005-01-01

The NPT rests on three interlinked pillars: cooperation in peaceful uses of nuclear energy, verified nuclear non-proliferation, and nuclear disarmament. This article looks specifically at the first pillar and its linkage with the second one. Non-nuclear weapon States are the vast majority of NPT Parties. The right of NPT Parties to have access to information, exchange of equipment and materials is explicitly recognized in Article IV of the Treaty. This Article stipulates that all Parties of the Treaty undertake to facilitate and have the right to participate in the fullest possible exchange of equipment, materials and scientific and technological information for the peaceful uses of nuclear energy. A successful campaign after the 1995 NPT Review Conference increased the NPT membership from 178 to near universality, and today 189 States are Parties to the Treaty. In the same period the IAEA's membership increased from 127 to 138. Today all IAEA Member States are participating in the Agency's Technical Cooperation Programme (TCP) in varying mixed capacities of donors or recipients. The IAEA, although not referred to in Article IV of the NPT, plays a major role in planning and implementing multilateral cooperation stipulated in the Treaty. It encourages and assists research, development and application of atomic energy; it provides technical advice, training, materials, services and equipment; fosters exchange of scientific and technical information; develops standards and guidelines for the appropriate utilization of nuclear technology and materials, and builds strategic partnerships to increase the leverage of the limited resources available. At all times, the Agency seeks to support the use of nuclear technology in a way that is safe for humans and the environment. All these activities are related to key statutory functions of the IAEA. Efforts to assist Member States are impressive. Since its inception in 1957, the Agency has provided direct assistance valued at

IAEA Leads Operational Safety Mission to Smolensk Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) has reviewed the Smolensk Nuclear Power Plant (NPP) near Desnogorsk, in Russia's Smolensk region, for its safety practices and has noted a series of good practices as well as recommendations and suggestions to reinforce them. The IAEA assembled the team at the request of the Government of the Russian Federation to conduct an Operational Safety Review (OSART) of the NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 5 to 22 September 2011. The team was made up of experts from China, India, Lithuania, Slovakia, South Africa, Sweden, UK, USA, the World Association of Nuclear Operators and the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Smolensk NPP. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; and Chemistry. Throughout the review, the exchange of information between the OSART experts and plant personnel was very open, professional and productive. The plant's staff were found to be motivated, well trained, knowledgeable and experienced. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include the following: Illuminated hot-spot wire to identify higher radiation levels is used in the radiation-controlled area to reduce exposures when working in the controlled area; Modern and state-of-the-art training infrastructure and facilities are available at the plant. These include: maintenance training centre; multimedia simulator for the refueling machine; and safety

Public information activities of the IAEA

International Nuclear Information System (INIS)

Meyer, Hand-Friedrich

1998-01-01

Since the accident at Three Mile Island in 1979 and increasingly since the Chernobyl accident 1986, the Division of Public Information (DPI) of the IAEA has become a contact point for journalists on all questions related to the nuclear energy and nuclear applications. The IAEA receives a continuously growing number of hits on its Internet Homepage. This is followed by an increasing number of E-mail letters from all over the world. The three main fields of general information activities of the IAEA's DPI are: 1 - the verification system of IAEA in the framework of international treaties concerning non-proliferation of nuclear weapons; 2 - the IAEA's work for safe operation of nuclear installations and its many services to improve the safe application of radiation and isotopes as well as safe operation of nuclear power plants. Questions on illicit trafficking and dangers of wrongly applied radiation sources play an important factor in our public information work in the field of nuclear safety; 3 - the IAEA's activities in the transfer of technology and the application of radiation and isotopes in agriculture, health, industry, hydrology and research. In addition to the new ways of providing information on the IAEA there is still the long established means of contact through periodicals like 'IAEA Bulletin' and 'IAEA Newsbriefs' or general information films like, for instance, 'The International Atom', 'The Nuclear Age', 'How a nuclear power plant works', 'Nuclear Energy and the Environment', 'The Safe Transport of Radioactive Material', 'The International Chernobyl Project', 'Mission Iraq' and others. Besides, there are aspects on longer lasting perspectives which should be considered: - physics teaching at schools; - information on nuclear fission, nuclear power, radiation and isotopes in a science museum in the capital; an information center at nuclear research facilities in the country. Nuclear has many advantages but it is difficult these days to convince normal

Safety Experts Complete IAEA Nuclear Regulatory Review of the United States

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of senior nuclear safety experts today completed a two-week International Atomic Energy Agency (IAEA) review of the governmental and regulatory framework for nuclear safety in the United States. The team identified good practices within the U.S. system and offered suggestions for ways the U.S. Nuclear Regulatory Commission (NRC) could improve. The IAEA has conveyed the team's main conclusions to the NRC, and a final report will be submitted to the NRC in about two months. At the request of the United States, the IAEA assembled a team of 19 international experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This mission was a peer review based on the IAEA Safety Standards. It was not an inspection, nor an audit. The experts came from 14 different countries: Canada, China, the Czech Republic, Finland, France, Italy, Japan, Mexico, the Republic of Korea, Slovenia, Spain, Sweden, Switzerland, and the United Kingdom. Team leader Jukka Laaksonen of Finland said: ''We found a comprehensive, consistent, and mature regulatory system run by the NRC, which has a strong drive for continuous improvement.' The scope of the mission included the U.S. regulatory framework and the regulation of the nuclear plant operation. The mission was conducted from 18 to 29 October, mainly at NRC headquarters outside of Washington, D.C. To study U.S. regulatory activities, the mission conducted a series of interviews and discussions with NRC staff and other organizations to help assess the effectiveness of the regulatory system. In addition, the team observed regulatory activities at two operating nuclear power reactors and an emergency preparedness exercise. The IAEA's IRRS coordinator Gustavo Caruso said, ''This mission represents a milestone for the IRRS program because the U.S. regulatory system is the largest in the world and many nations look to it. The IRRS is a useful tool that allows host nations to gain guidance from experienced

Analysis on IAEA 2006-2007 Programme and Cooperation Directions between Korea and IAEA

International Nuclear Information System (INIS)

Oh, Keun Bae; Lee, H. M.; Yang, M. H.; Lee, B. W.; Ko, H. S.; Ryu, J. S.; Kim, H. J.; Kim, K. P.

2004-12-01

In this study, the structure of the IAEA programme and the major changes in 2004/2005 programme cycle are analyzed. Also renewed programming process and major issues in 2006/2007 programme and budget are analyzed. Based on the analyses, the detailed proposal to strengthen cooperation with IAEA is prepared in the fields of nuclear power, nuclear application, nuclear safety and nuclear cooperation. As a result, the following 9 themes are identified to strengthen the relation between Korea and the IAEA. - Nuclear Production of Hydrogen - Sea Water Desalination - Nuclear Knowledge Management - Application of Food Irradiation - Cancer Treatment using Cyclotron - Global Nuclear Safety Network; - Management of Radiation Source by Global Positioning System (GPS) - Global Network for Radiological Emergency Response - Enhanced relationship between Regional Cooperation Frameworks

International physical protection standards: support for development and implementation

International Nuclear Information System (INIS)

Soo Hoo, M.S.

2002-01-01

Full text: Since 1972, the IAEA has been a recognized organization in promoting the development of international standards on the physical protection of nuclear materials. This responsibility has continued through the present in the 1999 publication of the fourth revision of INFCIRC/225, the physical protection of nuclear material and nuclear facilities and in being the repository for the convention on the physical protection of nuclear material which was originally published in 1980 as INFCIRC/274. The IAEA has also published other reference documents in support these two standards. With changing world events and greater concern for the physical protection of nuclear materials and facilities, IAEA member states have increased IAEA physical protection responsibilities. Currently, the IAEA is serving as the secretariat for drafting revisions to the physical protection convention. The proposed revisions will strengthen international physical protection standards through the incorporation of physical protection fundamentals that should apply to all nuclear materials in international or domestic use, storage and transport. Furthermore, the physical protection fundamentals would also extend to include nuclear facilities. Presently, the physical protection convention applies only to nuclear materials that are in international transport. To complement efforts to develop and promote international physical protection standards, the IAEA is actively involved in assisting member states with the implementation of the standards. This is accomplished through the delivery of training courses, workshops and hosting other international forums for the exchange of information. Through review services such as the international physical protection advisory service (IPPAS), the IAEA provides advice to member states on the application of international standards at national and facility-specific levels. These services can be followed up with technical support to implement the

Concept for a primary Romanian radon standard

International Nuclear Information System (INIS)

Sahagia, M.; Stanga, D.; Waetjen, A.C.; Luca, A.; Toro, L.; Varlam, C.; Cassette, P.

2008-01-01

The paper presents the concept of a complex system, aimed to assure the traceability of 222 Rn measurements, from the absolute (primary) standardization to the preparation and delivery of secondary standards, gas vials. The system will contain a solid 226 Ra source, a gas radon circuit, connections with a liquid scintillator vial and with glass vials. The absolute standardization of the 222 Rn, in equilibrium with all the short half life daughters, will be performed by the method of the Liquid Scintillation Counting (LSC). The system, and method, will allow our laboratory to take part in future international 222 Rn comparisons. The transfer of activity unit from the primary to the secondary standardization will be performed by the preparation of vials with 222 Rn gas, comparative measurements by LSC and a GeHP gamma-ray spectrometry system, or a well type NaI(Tl) crystal, and their link. The secondary standards will be used for the calibration of measurement instruments, for assurance of controlled radon atmosphere in 'radon chambers', and for the validation of some calculation models for various detectors efficiency. The range of activities for secondary standards is in agreement with the national measurement necessities. (author)

IAEA film library

International Nuclear Information System (INIS)

1959-01-01

Most of the scientific and technical films shown during the Second Geneva Conference for the Peaceful Uses of Atomic Energy were donated to IAEA by the producing countries at the end of the Conference. They will form the basic stock for the Agency's loan service intended to provide atomic energy institutions in Member States with film material. A detailed catalogue of the films, classified according to subject and giving conditions of loan or purchase, is now being prepared. In addition to this, information on all films produced in Member Countries dealing with the peaceful uses cf atomic energy is being assembled. The documentary information contained in the films in IAEA's possession relates to the following subjects: national programmes; nuclear physics; accelerators; plasma and fusion; reactors (power, research, material testing and experimental); prospecting and mining; ore dressing; metallurgy; production of fuel elements; treatment of irradiated fuel elements; protection against radiation; detection and counting; uses of radiation in medicine, biochemistry, agriculture and industry; industrial application of nuclear explosions. Most of the commentaries are in the language of the producing country. A few films are available in a choice of two languages. The films donated to the Agency total 82, two of which have been produced in Canada, 13 in France, one in India, one in Romania, one in Spain, 14 in the United Kingdom, one in the Union of South Africa, 47 in the United States of America and two in the USSR: they are mostly illustrations of papers presented at the Second Geneva Conference. In arranging for the circulation of scientific and technical films IAEA wishes to help meet some of the training and information needs of Member States. It is hoped that all organizations producing films on the peaceful uses of atomic energy will entrust copies to the IAEA with a view to their widest possible circulation. In the meantime, the Agency's films have been given

IAEA film library

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-01-15

Most of the scientific and technical films shown during the Second Geneva Conference for the Peaceful Uses of Atomic Energy were donated to IAEA by the producing countries at the end of the Conference. They will form the basic stock for the Agency's loan service intended to provide atomic energy institutions in Member States with film material. A detailed catalogue of the films, classified according to subject and giving conditions of loan or purchase, is now being prepared. In addition to this, information on all films produced in Member Countries dealing with the peaceful uses cf atomic energy is being assembled. The documentary information contained in the films in IAEA's possession relates to the following subjects: national programmes; nuclear physics; accelerators; plasma and fusion; reactors (power, research, material testing and experimental); prospecting and mining; ore dressing; metallurgy; production of fuel elements; treatment of irradiated fuel elements; protection against radiation; detection and counting; uses of radiation in medicine, biochemistry, agriculture and industry; industrial application of nuclear explosions. Most of the commentaries are in the language of the producing country. A few films are available in a choice of two languages. The films donated to the Agency total 82, two of which have been produced in Canada, 13 in France, one in India, one in Romania, one in Spain, 14 in the United Kingdom, one in the Union of South Africa, 47 in the United States of America and two in the USSR: they are mostly illustrations of papers presented at the Second Geneva Conference. In arranging for the circulation of scientific and technical films IAEA wishes to help meet some of the training and information needs of Member States. It is hoped that all organizations producing films on the peaceful uses of atomic energy will entrust copies to the IAEA with a view to their widest possible circulation. In the meantime, the Agency's films have been given

IAEA Project UKR/4/003, Ukraine: Training for safe operation and management of nuclear power plants

International Nuclear Information System (INIS)

Kossilov, A.; Ivanytskyy, V.

1998-01-01

The IAEA Project UKR/4/003 was established with the aim to develop and upgrade Ukrainian NPP personnel training system in order to enhance the NPP operational safety and improve NPP management, through development of the SAT concept for personnel training

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards; - Integrated approach to the provision for the application of safety standards; and - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices; on the capability and reliability of the commissioning and operating personnel; on comprehensive instructions; and on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2007-01-01

The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2008-01-01

The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

IAEA Operational Safety Team Review Bohunice Nuclear Power Plant, Slovak Republic

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed Slovakia's Bohunice Nuclear Power Plant (BNPP) for its safety practices and has noted a series of good practices as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of Slovak Republic to conduct an Operational Safety Review (OSART) of Bohunice NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 1 to 18 November 2010. The team was made up of experts from Belgium, Canada, China, the Czech Republic, France, Sweden, the United Kingdom and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at BNPP conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely is under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. Long Term Operation assessment has been requested by the plant in addition to the standard OSART program. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: BNPP has implemented a comprehensive set of technical and organizational measures which have significantly reduced the production of liquid radioactive waste; BNPP has developed an automatic transfer of dosimetry data

Environment assessing for airborne radioactive particulate release-introduction of methods in IAEA safety report series No.19

International Nuclear Information System (INIS)

Meng, Dan; Yang, Liu; Shen, Fu; Yang, Yi; Ma, Yinghao; Ma, Tao; Zhang, Zhilong; Fu, Cuiming

2016-01-01

Airborne radioactive particulate in many important nuclear facilities (particularly nuclear power plants) will have a strong impact on the relative public dose if they are released into the corresponding environment traversing the stack or vents. The radiation protection researchers have regarded the relative environment assessing and estimation of public doses. And the model of assessing impact of discharges radioactive substance to the environment have been recommended by many international organizations (e.g. IAEA) with the nuclear energy safety and radiation protection. This paper introduced the generic models that were suggested by International Atomic Energy Agency (IAEA), for use in assessing the impact of discharges of radioactive substances to the environment (e.g. IAEA Safety Report Series No.19). The writers of this paper, based on the recommend methods, assessed the discharge limits in some airborne radioactive substances discharging standards. The reasons that IAEA method are introduced are mainly the following considerations: IAEA is one of international organizations with some authorities in the nuclear energy safety and radiation protection; and, more important, the recommend modes are operational methods rather than the methods having little operations such as that have used by some researchers. It is wish that the introduced methods in this paper can be referenced in draft or revise of the standards related to discharges of radioactive substances to the environment

Environment assessing for airborne radioactive particulate release-introduction of methods in IAEA safety report series No.19

Energy Technology Data Exchange (ETDEWEB)

Meng, Dan; Yang, Liu; Shen, Fu; Yang, Yi; Ma, Yinghao; Ma, Tao; Zhang, Zhilong; Fu, Cuiming [China Institute for Radiation Protection, Taiyuan (China)

2016-12-15

Airborne radioactive particulate in many important nuclear facilities (particularly nuclear power plants) will have a strong impact on the relative public dose if they are released into the corresponding environment traversing the stack or vents. The radiation protection researchers have regarded the relative environment assessing and estimation of public doses. And the model of assessing impact of discharges radioactive substance to the environment have been recommended by many international organizations (e.g. IAEA) with the nuclear energy safety and radiation protection. This paper introduced the generic models that were suggested by International Atomic Energy Agency (IAEA), for use in assessing the impact of discharges of radioactive substances to the environment (e.g. IAEA Safety Report Series No.19). The writers of this paper, based on the recommend methods, assessed the discharge limits in some airborne radioactive substances discharging standards. The reasons that IAEA method are introduced are mainly the following considerations: IAEA is one of international organizations with some authorities in the nuclear energy safety and radiation protection; and, more important, the recommend modes are operational methods rather than the methods having little operations such as that have used by some researchers. It is wish that the introduced methods in this paper can be referenced in draft or revise of the standards related to discharges of radioactive substances to the environment.

IAEA, Fukushima Prefecture Sign Cooperation Memorandum

International Nuclear Information System (INIS)

2012-01-01

Full text: IAEA Director General Yukiya Amano and the Governor of Fukushima Prefecture, Yuhei Sato, today signed a Memorandum of Cooperation confirming their willingness to implement concrete projects to help alleviate the consequences of the accident at TEPCO's Fukushima Daiichi Nuclear Power Station. The Memorandum, signed on the sidelines of the three-day Fukushima Ministerial Conference on Nuclear Safety, includes arrangements to promote cooperation in two key areas: one on radiation monitoring and remediation between the IAEA and Fukushima Prefecture, and the other on human health between the IAEA and Fukushima Medical University. The Memorandum also highlights plans for a training centre in Fukushima Prefecture to help reinforce emergency preparedness and response activities, supported by the Government of Japan and Fukushima Prefecture. An IAEA Response and Assistance Network (RANET) Capacity Building Centre will be designated, with IAEA radiation monitoring equipment to be deployed in case of need, and to provide training in emergency preparedness and response in Japan and the Asia Pacific region. 'With this framework, the wisdom of the international community as well as the IAEA will be utilised in the process of reconstruction in Fukushima', said Japan's Minister of Foreign Affairs, Koichiro Gemba, who attended the signing ceremony. 'I'm very much encouraged by the conclusion of this Memorandum and I believe this will serve to promote reconstruction in Fukushima', said Governor Sato. 'We will also be able to disseminate to the rest of the world the knowledge and experience to be gained from the activities that we are conducting, and we hope this will be a symbol of Fukushima'. 'The IAEA has expertise in the areas of remediation and decontamination, as well as environmental monitoring and human health'. said Director General Amano. 'It is our hope that we will support Fukushima and at the same time serve as a bridge connecting the Prefecture and the world

The FAO/IAEA External Quality Assurance Programme (EQAP) and movement towards a generic veterinary diagnostic testing laboratory accreditation scheme. Report of an FAO/IAEA consultants meeting

International Nuclear Information System (INIS)

2002-01-01

FAO/IAEA support in the area of animal health is focused on enhancing the ability of regional reference laboratories and national veterinary authorities in developing countries to diagnose livestock diseases of major importance using nuclear and related technologies, and to help monitor the effectiveness of national and regional intervention strategies. This is done through provision of advice to the veterinary authorities concerning the development of appropriate sampling or research strategies coupled with FAO/IAEA-led collaborative development, adaptation, standardization, evaluation, and provision of quality-controlled enzyme-linked immunosorbent assay (ELISA) kits and the components necessary for diagnostic application of the polymerase chain reaction (PCR) techniques. Additional features of FAO/IAEA animal health support include provision of relevant laboratory equipment, training of counterpart scientists and technicians in the use of the equipment and standardized assays, and coordination of quality assurance (QA) programmes to monitor the proficiency of the assayists and help evaluate the impact of improved diagnostic capabilities. The current FAO/IAEA External Quality Assurance Programme (EQAP) for Animal Disease Diagnosis began as an effort to monitor the efficacy of mass vaccination programmes as part of the Pan African Rinderpest Campaign (PARC). Proficiency test panels, composed of 40 'unknown' serum samples, were sent to participating laboratories yearly to measure their abilities with ELISA in distinguishing between samples that were positive or negative for rinderpest antibodies. From this beginning, the EQAP has grown into an effort to measure general and specific components of FAO/IAEA counterparts' QA systems and provide assurance to outside observers that the use of FAO/IAEA diagnostic ELISA's are within established control limits and the test results and diagnostic interpretations are reliable. A major objective of the current EQAP is to

IAEA activities related to ITER

International Nuclear Information System (INIS)

Dolan, T.J.; Schneider, U.

2001-01-01

As agreed between the IAEA and the ITER Parties, special sessions are dedicated to ITER at the IAEA Fusion Energy Conferences. At the 18th IAEA Fusion Energy Conference, held on 4-10 October 2000 in Sorrento, Italy, in the Artsimovich-Kadomtsev Memorial opening session there were special lectures by Carlo Rubbia (President, ENEA, Italy), A. Arima (Japan), and E.P. Velikhov (Russia); an overview talk on ITER by R. Aymar (ITER Director); and a talk on the FTU experiment by F. Romanelli. In total, 573 participants from 34 countries presented 389 papers (including 11 post-deadline papers and the 4 summaries)

Review of the IAEA fire symposium

International Nuclear Information System (INIS)

Fischer, J.

1991-01-01

The IAEA Symposium on Fire Protection and Fire Fighting in Nuclear Installations covered a large scope in the field in order to provide the opportunity for screening all aspects of present technology, research and development, standardization, licensing and fire fighting practices. Although application to any nuclear facility was within its scope, the majority of presentations concerned nuclear power plants. The approach to fire protection is the classical one in all plant designs: reduction of fire loads, appropriate zoning, manual and automatic extinguishment. However, methods of analysis and consequence prediction are changing. Computerized fire modelling is becoming a powerful tool in this area; probabilistic analytical methods are being improved, though they are not yet used widely for fire hazards. Differences in opinion were revealed in the definition of barrier resistance, the prediction of cable insulation behaviour and the optimal design of extinguishing systems. Greater international co-operation, especially in these areas, may be a good way of optimizing results with limited resources. Discussion contributions showed interest in exchange of experience in more specialized topics and encouraged the IAEA to increase its activity in the area of fire protection. (orig.)

23rd IAEA Fusion Energy Conference: summary of sessions EX/C and ICC

International Nuclear Information System (INIS)

Hawryluk, R.J.

2011-01-01

An overview is given of recent experimental results in the areas of innovative confinement concepts, operational scenarios and confinement experiments as presented at the 2010 IAEA Fusion Energy Conference. Important new findings are presented from fusion devices worldwide, with a strong focus towards the scientific and technical issues associated with ITER and W7-X devices, presently under construction.

23rd IAEA Fusion Energy Conference: Summary Of Sessions EX/C and ICC

International Nuclear Information System (INIS)

Hawryluk, Richard J.

2011-01-01

An overview is given of recent experimental results in the areas of innovative confinement concepts, operational scenarios and confinement experiments as presented at the 2010 IAEA Fusion Energy Conference. Important new findings are presented from fusion devices worldwide, with a strong focus towards the scientific and technical issues associated with ITER and W7-X devices, presently under construction.

23rd IAEA Fusion Energy Conference: Summary Of Sessions EX/C and ICC

Energy Technology Data Exchange (ETDEWEB)

Hawryluk, R J [PPPL

2011-01-05

An overview is given of recent experimental results in the areas of innovative confinement concepts, operational scenarios and confinement experiments as presented at the 2010 IAEA Fusion Energy Conference. Important new findings are presented from fusion devices worldwide, with a strong focus towards the scientific and technical issues associated with ITER and W7-X devices, presently under construction.

IAEA safeguards for the Fissile Materials Disposition Project

International Nuclear Information System (INIS)

Close, D.A.

1995-06-01

This document is an overview of International Atomic Energy Agency (IAEA) safeguards and the basic requirements or elements of an IAEA safeguards regime. The primary objective of IAEA safeguards is the timely detection of the diversion of a significant quantity of material and the timely detection of undeclared activities. The two important components of IAEA safeguards to accomplish their primary objective are nuclear material accountancy and containment and surveillance. This overview provides guidance to the Fissile Materials Disposition Project for IAEA inspection requirements. IAEA requirements, DOE Orders, and Nuclear Regulatory Commission regulations will be used as the basis for designing a safeguards and security system for the facilities recommended by the Fissile Materials Disposition Project

Excerpts from the introductory statement by IAEA Director General. IAEA Board of Governors, Vienna, 9 December 1999

International Nuclear Information System (INIS)

ElBaradei, M.

1999-01-01

The document contains excerpts from the Introductory Statement made by the Director General of the IAEA at the IAEA Board of Governors on 9 December 1999. The following aspects from the Agency's activity are briefly presented: IAEA's safeguards, physical protection of nuclear material, the status of Agency's involvement in safeguards verification in the Democratic People's Republic of Korea (DPRK), and Agency's actions in connection with Y2K possible problems

Recommended observational skills training for IAEA safeguards inspections. Final report: Recommended observational skills training for IAEA safeguards inspections

Energy Technology Data Exchange (ETDEWEB)

Toquam, J.L.; Morris, F.A.

1994-09-01

This is the second of two reports prepared to assist the International Atomic Energy Agency (IAEA or Agency) in enhancing the effectiveness of its international safeguards inspections through inspector training in {open_quotes}Observational Skills{close_quotes}. The first (Phase 1) report was essentially exploratory. It defined Observational Skills broadly to include all appropriate cognitive, communications, and interpersonal techniques that have the potential to help IAEA safeguards inspectors function more effectively. It identified 10 specific Observational Skills components, analyzed their relevance to IAEA safeguards inspections, and reviewed a variety of inspection programs in the public and private sectors that provide training in one or more of these components. The report concluded that while it should be possible to draw upon these other programs in developing Observational Skills training for IAEA inspectors, the approaches utilized in these programs will likely require significant adaption to support the specific job requirements, policies, and practices that define the IAEA inspector`s job. The overall objective of this second (Phase 2) report is to provide a basis for the actual design and delivery of Observational Skills training to IAEA inspectors. The more specific purposes of this report are to convey a fuller understanding of the potential application of Observational Skills to the inspector`s job, describe inspector perspectives on the relevance and importance of particular Observational Skills, identify the specific Observational Skill components that are most important and relevant to enhancing safeguards inspections, and make recommendations as to Observational Skills training for the IAEA`s consideration in further developing its Safeguards training program.

IAEA code and safety guides on quality assurance

International Nuclear Information System (INIS)

Raisic, N.

1980-01-01

In the framework of its programme in safety standards development, the IAEA has recently published a Code of Practice on Quality Assurance for Safety in Nuclear Power Plants. The Code establishes minimum requirements for quality assurance which Member States should use in the context of their own nuclear safety requirements. A series of 10 Safety Guides which describe acceptable methods of implementing the requirements of specific sections of the Code are in preparation. (orig.)

Certified reference materials for radionuclides in Bikini Atoll sediment (IAEA-410) and Pacific Ocean sediment (IAEA-412)

DEFF Research Database (Denmark)

Pham, M. K.; van Beek, P.; Carvalho, F. P.

2016-01-01

The preparation and characterization of certified reference materials (CRMs) for radionuclide content in sediments collected offshore of Bikini Atoll (IAEA-410) and in the open northwest Pacific Ocean (IAEA-412) are described and the results of the certification process are presented. The certified...... radionuclides include: 40K, 210Pb (210Po), 226Ra, 228Ra, 228Th, 232Th, 234U, 238U, 239Pu, 239+240Pu and 241Am for IAEA-410 and 40K, 137Cs, 210Pb (210Po), 226Ra, 228Ra, 228Th, 232Th, 235U, 238U, 239Pu, 240Pu and 239+240Pu for IAEA-412. The CRMs can be used for quality assurance and quality control purposes...

Typical IAEA operations at a fuel fabrication plant

International Nuclear Information System (INIS)

Morsy, S.

1984-01-01

The IAEA operations performed at a typical Fuel Fabrication Plant are explained. To make the analysis less general the case of Low Enriched Uranium (LEU) Fuel Fabrication Plants is considered. Many of the conclusions drawn from this analysis could be extended to other types of fabrication plants. The safeguards objectives and goals at LEU Fuel Fabrication Plants are defined followed by a brief description of the fabrication process. The basic philosophy behind nuclear material stratification and the concept of Material Balance Areas (MBA's) and Key Measurement Points (KMP's) is explained. The Agency operations and verification methods used during physical inventory verifications are illustrated

IAEA Leads Operational Safety Mission to Armenian Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed the Armenian Nuclear Power Plant (ANPP) near Metsamor for its safety practices and has noted a series of good practices, as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of the Republic of Armenia to conduct an Operational Safety Review (OSART) of the NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 16 May to 2 June 2011. The team was made up of experts from Finland, France, Lithuania, Hungary, Netherlands, Slovakia, UK, USA, EC and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. Experts participating in the IAEA's June 2010 International Conference on Operational Safety of Nuclear Power Plants (NPP) reviewed the experience of the OSART programme and concluded: In OSART missions NPPs are assessed against IAEA safety standards which reflect the current international consensus on what constitutes a high level of safety; and OSART recommendations and suggestions are of utmost importance for operational safety improvement of NPPs. Armenia is commended for openness to the international nuclear community and for actively inviting IAEA safety review missions to submit their activities to international scrutiny. Examples of IAEA safety reviews include: Design Safety Review in 2003; Review of Probabilistic Safety Assessment in 2007; and Assessment of Seismic Safety Re-Evaluation in 2009. The team at ANPP conducted an in-depth review of the aspects essential to the safe operation of the plant, which is largely under the control of the site management

IAEA Newsbriefs. V. 9, no. 4(66). Oct 1994

International Nuclear Information System (INIS)

1994-01-01

This issue gives brief information on the following topics: IAEA Analyzing effect of US-DPRK Agreed Framework, Statement to General Assembly in New-York, Council on Foreign Relations, 19 October 1994, Congress of the European Nuclear Society, 4 October 1994, IAEA General Conference, 19 September 1994, Illicit Trafficking in Nuclear Materials, IAEA Director General Blix honoured, Ukraine and IAEA sign Safeguards Agreement, International Convention on Nuclear Safety, Highlights of the 1994 General Conference, IAEA safeguards in the DPRK, Monitoring and verification in Iraq, IAEA safeguards system, Measures against illicit trafficking in nuclear materials, African nuclear-weapon-free zone, South Africa's participation in IAEA activities, Application of IAEA safeguards in the Middle East, IAEA technical co-operation activities, Technical assistance in the Middle East, Radioactive waste management, Water resources and production, IAEA budget and extrabudgetary resources for 1995, Staffing of the IAEA Secretariat, Nuclear safety and radiological protection, Scientific Programme at the General Conference, Environmental monitoring, High-energy accelerators and radioactive waste management, Global food security and sustainability, Other meetings, Air Transport of Radioactive materials, Accelerators for Research, Water Resources, Radiation Technologies in Health Care, Spent Fuel Storage, Nuclear Techniques in Agriculture, Comprehending Radiation Risks, Environmental Impact of Radioactive Releases, Strengthening Radiation Protection Infrastructures, and other short information

IAEA Newsbriefs. V. 9, no. 4(66). Oct 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

This issue gives brief information on the following topics: IAEA Analyzing effect of US-DPRK Agreed Framework, Statement to General Assembly in New-York, Council on Foreign Relations, 19 October 1994, Congress of the European Nuclear Society, 4 October 1994, IAEA General Conference, 19 September 1994, Illicit Trafficking in Nuclear Materials, IAEA Director General Blix honoured, Ukraine and IAEA sign Safeguards Agreement, International Convention on Nuclear Safety, Highlights of the 1994 General Conference, IAEA safeguards in the DPRK, Monitoring and verification in Iraq, IAEA safeguards system, Measures against illicit trafficking in nuclear materials, African nuclear-weapon-free zone, South Africa`s participation in IAEA activities, Application of IAEA safeguards in the Middle East, IAEA technical co-operation activities, Technical assistance in the Middle East, Radioactive waste management, Water resources and production, IAEA budget and extrabudgetary resources for 1995, Staffing of the IAEA Secretariat, Nuclear safety and radiological protection, Scientific Programme at the General Conference, Environmental monitoring, High-energy accelerators and radioactive waste management, Global food security and sustainability, Other meetings, Air Transport of Radioactive materials, Accelerators for Research, Water Resources, Radiation Technologies in Health Care, Spent Fuel Storage, Nuclear Techniques in Agriculture, Comprehending Radiation Risks, Environmental Impact of Radioactive Releases, Strengthening Radiation Protection Infrastructures, and other short information

IAEA expert review mission completes assessment of fuel cleaning incident at Paks Nuclear Power Plant

International Nuclear Information System (INIS)

2003-01-01

Full text: The IAEA today completed its expert review mission to investigate the 10 April fuel cleaning incident at the Paks nuclear power plant in Hungary. The mission was requested by the Hungarian Government to provide an independent assessment of the causes and actions taken by the plant and Hungarian authorities. The team was composed of nuclear and radiation experts from the IAEA, Austria, Canada, Finland, Slovakia, the United Kingdom and the United States. In a press conference, team leader Miroslav Lipar highlighted the team's findings in five areas: On management, the team concluded that the Hungarian Atomic Energy Authority and Paks are committed to improving the safety of the plant. They noted that as a result of steam generator decontamination in previous years, deposits became attached to the fuel assemblies. A decision was made to clean the fuel and contract an outside company to develop and operate a fuel cleaning process. The team found that the design and operation of the fuel cleaning tank and system was not accomplished in the manner prescribed by the IAEA Safety Standards. Neither the Hungarian Atomic Energy Authority nor Paks used conservative decision-making in their safety assessments for this unproven fuel cleaning system. The team determined that there was an over-reliance on the contractor that had been selected for the design, management and operation of the fuel cleaning system. Time pressure related to a prescribed fuel outage schedule, combined with confidence generated by previous successful fuel cleaning operations, contributed to a weak assessment of a new design and operation, which involved fuel directly removed from the reactor following a planned shutdown. On regulatory oversight, the IAEA team concluded that the Hungarian Atomic Energy Authority underestimated the safety significance of the proposed designs for the fuel cleaning system, which resulted in a less than rigorous review and assessment than should have been necessary

IAEA coaches new entrants

International Nuclear Information System (INIS)

Jouette, I.

2016-01-01

IAEA provides new entrants in nuclear electricity production with a broad and integrated range of services. The aim is to make the new entrant full aware of the commitments and obligations linked to the development of a civil nuclear program. IAEA offers a 3-step approach. The first step assesses the elements the new entrants has to take into account to launch a nuclear program. The second step deals with the preliminary works before the construction starts but after the political decision to launch a nuclear program has been taken. At the end of the second step the national authorities are able to launch tenders and negotiate contracts for the construction of a nuclear power plant. The third step is dedicated to the necessary activities to implement the first nuclear power plant. The end of the third step means that national authorities are able to issue exploitation licenses for operating nuclear power stations. All along the IAEA accompaniment numerous meetings are scheduled in which IAEA experts meet the 3 organisations that represent the new entrant: the government, the plant operator and the national safety authority. An important element of the first step is to help the country to assess the necessary human resource in terms of qualified staff. (A.C.)

IAEA activities on research reactor safety

International Nuclear Information System (INIS)

Alcala-Ruiz, F.

1995-01-01

Since its inception in 1957, the International Atomic Energy Agency (IAEA) has included activities in its programme to address aspects of research reactors such as safety, utilization and fuel cycle considerations. These activities were based on statutory functions and responsibilities, and on the current situation of research reactors in operation around the world; they responded to IAEA Member States' general or specific demands. At present, the IAEA activities on research reactors cover the above aspects and respond to specific and current issues, amongst which safety-related are of major concern to Member States. The present IAEA Research Reactor Safety Programme (RRSP) is a response to the current situation of about 300 research reactors in operation in 59 countries around the world. (orig.)

IAEA statement on Iranian enrichment announcement

International Nuclear Information System (INIS)

2010-01-01

Full text: The following is a statement attributable to IAEA Spokesperson Gill Tudor: 'The IAEA can confirm that it has received a letter from the Atomic Energy Organization of Iran (AEOI) on 8 February 2010, in which the AEOI informed the Agency that production of less than 20% enriched uranium is being foreseen at the Pilot Fuel Enrichment Plant at Natanz for fuel for the Tehran Research Reactor'. 'IAEA Director General Yukiya Amano noted with concern this decision, as it may affect, in particular, ongoing international efforts to ensure the availability of nuclear fuel for the Tehran Research Reactor.' 'The Director General reiterated the Agency's readiness to play an intermediary role on the issue of the Tehran Research Reactor.' (IAEA)

Family Concepts in Early Learning and Development Standards

Science.gov (United States)

Walsh, Bridget A.; Sanchez, Claudia; Lee, Angela M.; Casillas, Nicole; Hansen, Caitlynn

2016-01-01

This exploratory study investigated the use of concepts related to families, parents, and the home in 51 state-level early learning and development standards documents. Guidelines from six national family involvement, engagement, and school-partnership models were used to create the Family Involvement Models Analysis Chart (FIMAC), which served as…

The IAEA's high level radioactive waste management programme

International Nuclear Information System (INIS)

Saire, D.E.

1994-01-01

This paper presents the different activities that are performed under the International Atomic Energy Agency's (IAEA) high level radioactive waste management programme. The Agency's programme is composed of five main activities (information exchange, international safety standards, R ampersand D activities, advisory services and special projects) which are described in the paper. Special emphasis is placed on the RADioactive WAste Safety Standards (RADWASS) programme which was implemented in 1991 to document international consensus that exists on the safe management of radioactive waste. The paper also raises the question about the need for regional repositories to serve certain countries that do not have the resources or infrastructure to construct a national repository

Sustaining IAEA Neutron Coincidence Counting: Past, Present and Future

International Nuclear Information System (INIS)

Longo, J.; Schaffer, K.M.; Nordquist, H.

2015-01-01

Los Alamos National Laboratory's IAEA Neutron Coincidence Counting (INCC) code is the standard tool for neutron coincidence counting measurements. INCC software and its' predecessors were originally implemented in the 1970s. The measurement and analysis techniques perfected in the code arise from many years of laboratory and field experience by nuclear engineers and physicists. Covering the full arc of INCC's lifecycle, we discuss the engineering approaches used for conception, original development, worldwide deployment of the stand-alone Windows application, more than a decade of sustained maintenance support, and our recent work to carry INCC successfully into future applications. We delve into the recent re-architecture of the INCC code base, an effort to create a maintainable and extensible architecture designed to preserve the existing INCC code base while adding support for new analyzes and instruments (e.g., List Mode PTR-32 and the List Mode Multiplicity Module). INCC now consists of separate modules implementing attended instrumentation control, data file processing, statistical and Pu mass calculation and analyzes, list mode counting and analyzes, reporting functions, and a database support library. Separating functional capabilities in this architecture enables better testing, isolates development risk and enables the use of INCC features in other software systems. We discuss our approach to handling divergent data and protocol support as a result of this re-architecture. INCC has complex testing requirements; we show how the testing effort was reduced by breaking the software into separate modules. This new architecture enables integration of INCC analysis into the IAEA's new Integrated Review and Analysis Programme (iRAP) data review system. iRAP is based on the respected Euratom Comprehensive Review Inspector Software Package (CRISP) software framework, and is expected to be the future data review system for IAEA and Euratom

Excerpts from the introductory statement. IAEA Board of Governors. Vienna, 19 March 2001

International Nuclear Information System (INIS)

ElBaradei, M.

2000-01-01

In his introductory statement to the IAEA Board of Governors, the IAEA Director General gave an overview of the Agency's activities regarding technological issues in nuclear power and non-power applications; safety issues related to nuclear power plants and research reactors; decommissioning of nuclear facilities; safety of radiation sources; and marine transport of radioactive materials. Further in the document he gives a brief description of the Agency's activities in the field of nuclear verification; Agency's participation in a field mission to Kosovo on environmental assessment of the consequences of the use of depleted uranium in ammunition; safety standards discussions with ICAO

IAEA Leads Nuclear Power Plant Mission in Republic of Korea

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) has reviewed the Wolsong 1 Nuclear Power Plant (NPP) near Gyeongju in the Republic of Korea for its strategy and key elements for safe long-term operation. The team has noted a series of good practices and performances as well as recommendations and suggestions to reinforce the plant's safety. The IAEA assembled the team at the request of the Government of the Republic of Korea to conduct a Safety Aspects of Long Term Operation (SALTO) Peer Review Mission of the NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the SALTO team performed an in-depth review from 29 May to 7 June 2012. The team was made up of experts from Canada, the Czech Republic, India, Japan, Switzerland, Sweden and the IAEA. The mission will review programs and activities essential to operational safety. It is not a regulatory inspection, a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team is conducting an in-depth review of those aspects, largely under the control of site management, which are essential to the safe operation of the nuclear power plant. The conclusions of the review will be based on the IAEA's Safety Standards. The team conducted an in-depth review of the aspects essential to the safe long-term operation of the Wolsong 1 NPP. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of organization and functions; configuration/modification management; safety analysis reports and existing plant programmes; electrical and instrumentation-and-control components and civil structures; and radiological environmental impact. ''Throughout the review, the exchange of information between the SALTO experts and plant personnel was very intensive,''said team leader Robert Krivanek of the IAEA's Division of Nuclear

IAEA Board of Governors approves IAEA action plan to combat nuclear terrorism

International Nuclear Information System (INIS)

2002-01-01

The IAEA Board of Governors today approved in principal an action plan designed to upgrade worldwide protection against acts of terrorism involving nuclear and other radioactive materials. In approving the plan, the Board has recognized that the first line of defense against nuclear terrorism is the strong physical protection of nuclear facilities and materials. 'National measures for protecting nuclear material and facilities are uneven in their substance and application,' the IAEA says. 'There is wide recognition that the international physical protection regime needs to be strengthened.'

Exposure due to radon in homes - an IAEA perspective

International Nuclear Information System (INIS)

Navratilova-Rovenska, K.; Boal, T.; Colgan, T.

2014-01-01

The results of miner and residential epidemiology studies provide statistically strong evidence of harmful effects of exposure due to radon and its progeny. With the publication of the fifth edition of the International Basic Safety Standards, of the World Health Organizations Handbook on Indoor Radon and new ICRP statement on radon, there is increased interest from the public health and radiation protection authorities on controlling exposure due to radon and its progeny.The IAEA Safety Requirements publication 'Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards' sets out requirements on governments for control of existing exposure situations, which includes exposure due to radon. The types of situation that are included in the scope of existing exposure situations include exposure in workplaces for which the exposure due to radon is not required by or directly related to the work and for which annual average activity concentrations due to 222 Rn must not exceed a maximum reference level of 1000 Bq/m 3 annual activity concentration, as well as exposure in dwellings and in other buildings with high occupancy factors for members of the public for which the reference level must not exceed a maximum value of 300 Bq/m 3 . These requirements include: collecting data on the activity concentrations of radon in dwellings and other buildings with high occupancy by the public; providing information on exposure due to radon and the associated health risks; and if necessary, to develop an action plan for controlling public exposure to radon. The IAEA has developed a Safety Guide to provide guidance on developing the radon action plan: 'Protection of the Public against Exposure Indoors due to Radon and Other Natural Sources of Radiation'. This presentation will summarize the information on the assistance that the IAEA is currently providing to IAEA Member States to develop radon action plans. These activities include

IAEA Safeguards: Status and prospects

International Nuclear Information System (INIS)

Gruemm, H.

1983-01-01

The IAEA has just celebrated its 25th anniversary, and the first safeguards inspections were performed twenty years ago. Counting only since 1978, some 5100 inspections had been performed up to mid-1982, using a staff which now includes about 130 inspectors. Despite these impressive figures, and the fact that the IAEA has never detected any apparent diversion of nuclear materials, there are increasing public allegations that safeguards lack effectiveness. After briefly reviewing the nature of IAEA safeguards agreements, the paper examines the political and technical objectives of safeguards together with some of the criticisms which have been voiced. Allocation of limited safeguards resources is examined in terms of the sometimes conflicting allocation criteria which are contained in various safeguards documents. The paper argues that the credibility and deterrent effect of IAEA safeguards should not be underestimated. It should be of greater concern that a few States are known to be operating or constructing non-safeguarded nuclear facilities capable of producing weapons-grade nuclear materials. Thus the risk of safeguards would appear to be greatest at exactly the point where safeguards end. (author)

Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material (2005 Ed.). Safety Guide (Spanish Edition); Listas de disposiciones del reglamento del OIEA para el transporte seguro de materiales radiactivos (Edicion de 2005 corregida)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-12-15

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

The IAEA Integrated Regulatory Review Service (IRRS) - Information Meeting Dublin

International Nuclear Information System (INIS)

Al Khatibeh, Ahmad

2014-05-01

IRRS is developed to help States evaluate the current status of compliance of their regulatory infrastructures for safety with IAEA Standards. This report discusses the function of IRRS missions as a tool for evaluating the regulatory structure for Member States. It was presented to RPII staff in a Powerpoint document in preparation for the IRRS Mission to Ireland in August 2015

Protection of the patient in medical exposure - the related IAEA safety guide

International Nuclear Information System (INIS)

Turai, I.

1999-01-01

The Radiation Safety Section of the Agency has recently completed the draft Safety Guide on Radiation Protection in Medical Exposures' for submission to the Publication Committee of the IAEA. The author as served as one of the scientific secretaries responsible for the preparation and review of this document in the last two years. The drafts of this IAEA Safety Guide have undergone a detailed review process by specialists of 14 Member States and the co-sponsoring organizations, the Pan American Health Organization and the World Health Organization (WHO). The last draft is the primary source of this paper. The Safety Guide will be part of the Safety Standards Series. It is addressed to Regulatory Authorities and other National Institutions to provide them with guidance at the national level on the practical implementation of Appendix II (Medical Exposure) of the International Basic Safety Standards for the Protection against Ionizing Radiation and for the Safety of Radiation Sources

IAEA safety glossary. Terminology used in nuclear, radiation, radioactive waste and transport safety. Version 1.0. Working material

International Nuclear Information System (INIS)

2000-04-01

The IAEA safety standards for nuclear installations, radiation protection, radioactive waste management and the transport of radioactive materials have been historically developed in four separate programmes, each of them developing its own terminology. The purpose was to explain the meaning of technical terms that might be unfamiliar to a reader; to explain any special meanings assigned to common words or terms and to define precisely how terms are used in particular publications to avoid ambiguity concerning some important aspects of their meaning. It is intended primarily to provide guidance to the drafters and reviewers of Agency safety related publications, including IAEA Technical officers, consultants and members of Technical Committees, Advisory Groups and safety standards advisory bodies. It is also likely to be a useful source of information for other Agency staff, notably editors and translators, and for external users of IAEA safety related publications

IAEA Concludes Safety Review at Chooz Nuclear Power Plant in France

International Nuclear Information System (INIS)

2013-01-01

Full text: An IAEA-led international team of nuclear safety experts noted good practices and made recommendations to reinforce safety measures during a review of operational safety at France's Chooz Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 17 June, focused on aspects essential to the safe operation of the NPP. The team comprised experts from Switzerland, Belgium, Germany, China, India, United Kingdom, Czech Republic, Canada, Hungary and the IAEA. The review covered the areas of management, organization and administration; training and qualification of personnel; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team identified good plant practices that will be shared with the rest of the nuclear industry for consideration. Examples include: The plant has a professional development programme as part of a joint employment effort shared by the plant and its contractors. This enables trainees to develop professional capability, understand practices and gain experience from other nuclear power plants in terms of work planning and coordination; The plant has built a strong relationship between the on-shift response team of the plant and the local fire brigade to improve firefighting and rescue operations; Self-assessment groups discuss and resolve specific issues within operations, empowering operations personnel to take ownership of improvement programmes; and The plant has improved warnings at entrances to all o range zones , areas of elevated dose rates to which only authorized staff have access. The team identified a number of improvements to operational safety at Chooz NPP. Examples include: The plant should review its process for the

IAEA safeguards: some pros and cons

International Nuclear Information System (INIS)

Kelly, P.

1986-01-01

The author gives a personal view of the International Atomic Energy Agency's (IAEA) safeguards. The IAEA safeguards system is described (including containment, surveillance and inspection), and the limitations and strengths of the system are examined. (U.K.)

Tokamak concept innovations

International Nuclear Information System (INIS)

1986-04-01

This document contains the results of the IAEA Specialists' Meeting on Tokamak Concept Innovations held 13-17 January 1986 in Vienna. Although it is the most advanced fusion reactor concept the tokamak is not without its problems. Most of these problems should be solved within the ongoing R and D studies for the next generation of tokamaks. Emphasis for this meeting was placed on innovations that would lead to substantial improvements in a tokamak reactor, even if they involved a radical departure from present thinking

IAEA Newsbriefs. V. 10, no. 3(69). Nov-Dec 1995

International Nuclear Information System (INIS)

1995-01-01

This issue gives brief information on the following topics: IAEA Director General Addresses United Nations, IAEA Board of Governors' December Meetings, UN General Assembly Commends Work of IAEA, Oceanographic Investigations of Radioactive Pollution, Cancer Radiotherapy Using Heavy Charged Particles, Highlights of the 1995 IAEA General Conference, Director General's Statement to 1995 IAEA General Conference, General Conference Scientific Programme, Countries Invited to More Widely Apply INES Scale, Safety Meeting on Kozloduy in Bulgaria, Selection of Dry Storage Technologies for Spent Fuel, India Presents Sculpture to the IAEA, IAEA Seminars and Symposia, and other short information

The public information programme of the IAEA

International Nuclear Information System (INIS)

Meyer, Hans-Friedrich

1989-01-01

The public information programme of the IAEA is deter-mined by two basic criteria: First by the Statute of the IAEA which defines its objectives as 'to seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world' as well as 'to ensure as far as it is able, that assistance provided by it or at its request or under its supervision or control is not used in such a way as to further any military purpose'; second by the fact that the IAEA is an intergovernmental organization, which means that it has to fulfill request of independent, sovereign governments. In a discussion of the public infomation program of the IAEA, three main fields of activities always have to be kept in mind: Nuclear applications in agriculture, medicine, industry, hydrology, research, etc.; The use of nuclear energy for electricity generation, here mainly the aspects of safety and economics; and safeguards. From this it can be understood that the public information activities of the IAEA must have different perspectives: There are non-controversial fields for public information work, such as ost all aspects of nuclear application employing radiation and Isotopes. -- There are activities of the IAEA where the work in general is not questioned but considered absolutely necessary. -- There are finally controversial fields, where the IAEA is blamed for being too promotional. Examples are the IAEA's activities in nuclear power program planning as well as in food irradiation. In these controversial fields, it is very important to look for long-term, issue-oriented strategies to communicate good factual information in perspective

The public information programme of the IAEA

Energy Technology Data Exchange (ETDEWEB)

Meyer, Hans-Friedrich [Division of Public Information, International Atomic Energy Agency, Vienna (Austria)

1989-07-01

The public information programme of the IAEA is deter-mined by two basic criteria: First by the Statute of the IAEA which defines its objectives as 'to seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world' as well as 'to ensure as far as it is able, that assistance provided by it or at its request or under its supervision or control is not used in such a way as to further any military purpose'; second by the fact that the IAEA is an intergovernmental organization, which means that it has to fulfill request of independent, sovereign governments. In a discussion of the public infomation program of the IAEA, three main fields of activities always have to be kept in mind: Nuclear applications in agriculture, medicine, industry, hydrology, research, etc.; The use of nuclear energy for electricity generation, here mainly the aspects of safety and economics; and safeguards. From this it can be understood that the public information activities of the IAEA must have different perspectives: There are non-controversial fields for public information work, such as ost all aspects of nuclear application employing radiation and Isotopes. -- There are activities of the IAEA where the work in general is not questioned but considered absolutely necessary. -- There are finally controversial fields, where the IAEA is blamed for being too promotional. Examples are the IAEA's activities in nuclear power program planning as well as in food irradiation. In these controversial fields, it is very important to look for long-term, issue-oriented strategies to communicate good factual information in perspective.

Uncertainty and minimum detectable concentrations using relative, absolute and K*0-IAEA standardization for the INAA laboratory of the ETRR-2

International Nuclear Information System (INIS)

Khalil, M. Y.

2006-01-01

Full text: The Instrumental Neutron Activation Analysis (INAA) Laboratory of Egypt Second Training and Research Reactor (ETRR-2) is increasingly requested to perform multi-element analysis to large number of samples from different origins. The INAA laboratory has to demonstrate competence by conforming to appropriate internationally and nationally accepted standards. The objective of this work is to determine the uncertainty budget and sensitivity of the INAA laboratory measurements. Concentrations of 9 elements; Mn, Na, K, Ca, Co, Cr, Fe, Rb, and Cs, were measured against a certified test sample. Relative, absolute, and Ko-IAEA standardization methods were employed and results compared. The flux was monitored using cadmium covered gold method, and multifoil (gold, nickel and zirconium) method. The combined and expanded uncertainties were estimated. Uncertainty of concentrations ranged between 2-21% depending on the standardization method used. The relative method, giving the lowest uncertainty, produced uncertainty budget between 2 and 11%. The minimum detectable concentration was the lowest for Cs ranging between 0.36 and 0.59 ppb and the highest being for K in the range of 0.32 to 8.64 ppm

IAEA Newsbriefs. V. 10, no. 1(67). Mar-Apr 1995

International Nuclear Information System (INIS)

1995-01-01

This issue gives brief information on the following topics: IAEA Board to Consider Proposal on Safeguards, IAEA Director General to Address NPT Conference in mid-April, IAEA Hosts UN System-Wide Meeting, Joint IAEA/EC/WHO Conference on Chernobyl Announced, IAEA Concludes Post-Chernobyl Research Project, Uranium Data in Environmental Monitoring, Director General Address in Chile, South Africa, the Philippines Host Nuclear Information Seminars, Upcoming IAEA Conferences, Symposia and Seminars, Isotopes in Water Resources Management, Environmental Impacts of Radioactive Releases, Joint FAO/IAEA Symposium on Crop Improvement, Other Conferences, Symposia and Seminars in 1995, Safeguards and Non-Proliferation Developments (IAEA Safeguards Agreements, New NPT Members), Handbook on Nuclear Communications, SIT Campaign in Zanzibar, and other short information

IAEA programme on research reactor safety

International Nuclear Information System (INIS)

Alcala, F.; Di Meglio, A.F.

1995-01-01

This paper describes the IAEA programme on research reactor safety and includes the safety related areas of conversions to the use of low enriched uranium (LEU) fuel. The program is based on the IAEA statutory responsibilities as they apply to the requirements of over 320 research reactors operating around the world. The programme covers four major areas: (a) the development of safety documents; (b) safety missions to research reactor facilities; (c) support of research programmes on research reactor safety; (d) support of Technical Cooperation projects on research reactor safety issues. The demand for these activities by the IAEA member states has increased substantially in recent years especially in developing countries with increasing emphasis being placed on LEU conversion matters. In response to this demand, the IAEA has undertaken an extensive programme for each of the four areas above. (author)

IAEA Issues Report on Mission to Review Japan's Nuclear Power Plant Safety Assessment Process

International Nuclear Information System (INIS)

2012-01-01

Full text: A team of international nuclear safety experts has delivered its report on a mission it conducted from 21-31 January 2012 to review Japan's process for assessing nuclear safety at the nation's nuclear power plants. International Atomic Energy Agency (IAEA) officials delivered the IAEA Mission Report to Japanese officials yesterday and made it publicly available today. Following the 11 March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station, Japan's Nuclear and Industrial Safety Agency (NISA) announced the development of a revised safety assessment process for the nation's nuclear power reactors. At the request of the Government of Japan, the IAEA organized a team of five IAEA and three international nuclear safety experts and visited Japan to review NISA's approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. A Preliminary Summary Report was issued on 31 January. 'The mission report provides additional information regarding the team's recommendations and overall finding that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, Director of the IAEA's Nuclear Installation Safety Division. National safety assessments and their peer review by the IAEA are a key component of the IAEA Action Plan on Nuclear Safety, which was approved by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. The IAEA safety review mission held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety Organization (JNES), and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. In its report delivered today

Recommended observational skills training for IAEA safeguards inspections. Final report: Recommended observational skills training for IAEA safeguards inspections

International Nuclear Information System (INIS)

Toquam, J.L.; Morris, F.A.

1994-09-01

This is the second of two reports prepared to assist the International Atomic Energy Agency (IAEA or Agency) in enhancing the effectiveness of its international safeguards inspections through inspector training in open-quotes Observational Skillsclose quotes. The first (Phase 1) report was essentially exploratory. It defined Observational Skills broadly to include all appropriate cognitive, communications, and interpersonal techniques that have the potential to help IAEA safeguards inspectors function more effectively. It identified 10 specific Observational Skills components, analyzed their relevance to IAEA safeguards inspections, and reviewed a variety of inspection programs in the public and private sectors that provide training in one or more of these components. The report concluded that while it should be possible to draw upon these other programs in developing Observational Skills training for IAEA inspectors, the approaches utilized in these programs will likely require significant adaption to support the specific job requirements, policies, and practices that define the IAEA inspector's job. The overall objective of this second (Phase 2) report is to provide a basis for the actual design and delivery of Observational Skills training to IAEA inspectors. The more specific purposes of this report are to convey a fuller understanding of the potential application of Observational Skills to the inspector's job, describe inspector perspectives on the relevance and importance of particular Observational Skills, identify the specific Observational Skill components that are most important and relevant to enhancing safeguards inspections, and make recommendations as to Observational Skills training for the IAEA's consideration in further developing its Safeguards training program

Nuclear data services provided by the IAEA

International Nuclear Information System (INIS)

Schwerer, O.; Oblozinsky, P.

2001-01-01

This paper summarizes the various nuclear data types, libraries and services available free of charge from the IAEA Nuclear Data Section. The databases are collected, maintained and made available within the framework of an international nuclear data center's network. Particular emphasis is given to online services via the Internet. The URL address of the IAEA Nuclear Services is http://www-nds.iaea.or.at. (author)

The development of the IAEA policy on the radiological protection of the environment

International Nuclear Information System (INIS)

Linsley, G.

2002-01-01

Since its creation in 1957, and in accordance with its statute, the IAEA has established standards of safety for protection of health in the fields of nuclear installations safety, radiation protection, the transport of radioactive materials and radioactive waste management, including the control of radioactive releases to the environment. In this context, the IAEA has a long history of involvement in matters related not only to the protection of humans but also to the protection of other species from the effects of radioactivity in the environment. Concern about the environment has arisen for different reasons over the years, starting with questions about the potential effects on non-human species of fall-out from nuclear weapons testing and of radioactive discharges to atmosphere and the oceans. Later, the concern was focussed on the possible harm to non-human species caused by the dumping of solid waste at sea. The IAEA has responded to requests from other UN bodies and from international conventions to evaluate these potential hazards and to establish protection criteria. Social and political attitudes have gradually changed towards the environment mainly due to a growing realisation that the environment is vulnerable to the effects of human activities. This change has been reflected in the outcomes of major UN conferences on the environment in 1972 and 1992 and, accordingly, the emphasis of international and national policies towards the environment has increasingly shifted towards protective measures and strategies that include other species. Thus, the protection of the environment from the effects of ionising radiation has taken on a new importance. The IAEA, together with other relevant international organisations, is working to develop an agreed environmental protection strategy to counter the possible effects of ionising radiation, building on the work done over the last 30 years but taking due account of the new attitudes to the subject. The IAEA

Directory of IAEA databases

International Nuclear Information System (INIS)

1992-12-01

This second edition of the Directory of IAEA Databases has been prepared within the Division of Scientific and Technical Information (NESI). Its main objective is to describe the computerized information sources available to staff members. This directory contains all databases produced at the IAEA, including databases stored on the mainframe, LAN's and PC's. All IAEA Division Directors have been requested to register the existence of their databases with NESI. For the second edition database owners were requested to review the existing entries for their databases and answer four additional questions. The four additional questions concerned the type of database (e.g. Bibliographic, Text, Statistical etc.), the category of database (e.g. Administrative, Nuclear Data etc.), the available documentation and the type of media used for distribution. In the individual entries on the following pages the answers to the first two questions (type and category) is always listed, but the answers to the second two questions (documentation and media) is only listed when information has been made available

Public Conceptions of Algorithms and Representations in the Common Core State Standards for Mathematics

Science.gov (United States)

Nanna, Robert J.

2016-01-01

Algorithms and representations have been an important aspect of the work of mathematics, especially for understanding concepts and communicating ideas about concepts and mathematical relationships. They have played a key role in various mathematics standards documents, including the Common Core State Standards for Mathematics. However, there have…

Long term operation of nuclear power plants – IAEA SALTO peer review service and its results

Energy Technology Data Exchange (ETDEWEB)

Krivanek, Robert, E-mail: r.krivanek@iaea.org

2014-12-15

Highlights: • SALTO peer review service is designed for reviewing of ageing management and NPPs’ preparedness LTO. • It has been established as an effective tool to review the compliance with IAEA safety standards. • The important issues for safe LTO are being identified by SALTO missions. • Analysis of those issues is provided in the paper. • This peer review service is strongly recommended for NPPs prior to entering LTO period. - Abstract: This paper presents main IAEA activities for safe long term operation (LTO) which includes establishment of IAEA Safety Standards and other LTO related documents, fostering information exchange and establishing databases and provision of SALTO (Safety Aspects of Long Term Operation) peer review service. This paper provides insights into IAEA SALTO peer review service objectives, scope and methodology. The SALTO peer review service was designed to assist nuclear power plant (NPP) operators in adopting a proper approach to LTO of their plants and in implementing complete and appropriate activities to ensure that plant safety will be maintained during the LTO period. The SALTO peer review service can also support regulators in establishing or improving regulatory and licensing strategies for LTO of NPPs. Issues derived from 19 SALTO missions and 2 LTO modules of OSART (Operational Safety Review Team) missions conducted during the period of 2005 to March 2014 are also analyzed in this paper.

IAEA Newsbriefs. V. 14, no. 1(82). Jan-Feb 1999

International Nuclear Information System (INIS)

1999-01-01

This issue gives brief information on the following topics: 2000 Budget Goes Before IAEA Board of Governors, IAEA, Inspectors Relocated from Iraq, Review Meeting of Nuclear Safety Convention Set in April, Statements of IAEA Director General, The IAEA and Y2K Issues: Clearinghouse and Contact Point, Strengthened Safeguards System: Status of Additional Protocols, More States Join International Conventions in Nuclear Fields, IAEA International Scientific Symposia and Seminars in 1999, New IAEA Books, and othe short information

Correlation study among the International Atomic Energy Agency standards and market standards on management system applicable to a UF6 conversion plant operation

International Nuclear Information System (INIS)

Oliveira, Dirceu Paulo de

2008-01-01

The Agency - International Atomic Energy Agency (IAEA), following the market trend of the management system integration, has decided to revise the quality assurance standards - IAEA 50-C/SG-Q publishing, in 2006, the standard on Management System (MS). IAEA GS-R-3 and its IAEA GS-G-3.1 guide. Also, the IAEA is about to publish a supplementary guide - IAEA DS349, which consider the integration of several functions involved in management of nuclear facilities, such as: safety, health, environmental and quality, ensuring that nuclear safety is not compromised. Conversion plants of 'Yellowcake' in UF 6 use and process radioactive materials, as well as other substances normally found in the chemical conventional industry, inserting themselves in the organization profile that require a high pattern of definition, implementation and continuous improvement of their MS and, therefore, should consider an approach of management integrated system (MIS). Taking a UF 6 conversion plant as focus, the correlation was performed among the Agency MS standards and those of the market - ISO 9001, ISO 14001 and OHSAS 18001, as well as with the Agency drafts standards on safety (DS316 and DS344), concluding that, in structuring an MIS, in compliance with the Agency MS standards, except for some adjustments, the ISO 9001, ISO 14001, and OHSAS 18001 are going to be met. On the other hand, the structuring of MIS should identify other requirements on safety, health and environmental, which also consider the conventional chemical and industrial characteristics that are out of the scope (ionizing radiation) of the safety standards of the Agency. The research proposes a documental procedure for a MIS applicable to this plant, providing elements for rationalization and contents of the identified documentation, for the promotion of the integration of the considered MS functions. (author)

Concluding Statement to IAEA Ministerial Conference on Nuclear Safety, 24 June 2011, Vienna, Austria

International Nuclear Information System (INIS)

Amano, Y.

2011-01-01

Full text: This IAEA Ministerial Conference on Nuclear Safety has achieved its main goal, which was to pave the way for an enhanced post-Fukushima global nuclear safety framework. The result, in the words of the Ministerial Declaration agreed by you on Monday, will be a strengthening of nuclear safety, emergency preparedness, and radiation protection of people and the environment worldwide. I am grateful to all of you for your active participation and for the constructive spirit seen throughout the week's deliberations. The Ministerial Declaration outlines a number of measures to improve nuclear safety and expresses the firm commitment of IAEA Member States to ensure that these measures are actually implemented. Collectively, our Member States have expressed their sense of urgency, as well as their determination that the lessons of Fukushima Daiichi will be learned and that the appropriate action will be taken. I am grateful to you, Mr. President, and to the Chairs of the three Working Groups, for steering the Conference to its constructive conclusions. I also thank the keynote speakers, panellists and all participants for their valuable contributions. We have seen differences of opinion in some areas, which is entirely natural, but I am struck by how much broad agreement there has been on the fundamentals. I am particularly encouraged by the fact that the proposals I made in my opening statement on Monday enjoyed widespread support. As you may recall, these were: - to strengthen IAEA Safety Standards; - to systematically review the safety of all nuclear power plants, including by expanding the IAEA's programme of expert peer reviews ; - to enhance the effectiveness of national nuclear regulatory bodies and ensure their independence; - to strengthen the global emergency preparedness and response system; and - to expand the Agency's role in receiving and disseminating information. This is not about process - it is about results. The Declaration agreed here this week

Physical protection in relation to IAEA safeguards

International Nuclear Information System (INIS)

Sonnier, C.S.

1985-01-01

In this session, physical protection, nuclear material accounting and control, and containment and surveillance have been discussed, with emphasis on the interactions of these measures within the context of IAEA safeguards. In addition, the current physical protection equipment and techniques have been reviewed. The interactions can be summarized as follows. Although physical protection is a fundamental element of IAEA safeguards, it is solely a state/facility operator responsibility. While the IAEA has an interest in promoting the implementation of effective physical protection systems, it serves only in an advisory capacity. Nuclear material accounting directly involves the state, facility operator, and the IAEA. Facility records and reports provided by the state are independently verified by the IAEA. The SSAC is of fundamental importance in this process. Containment and surveillance measures are used by the UAEA. Installation and routine use of C/S equipment must be approved by the state and facility operator, and must not affect facility operations or safety

IAEA Assistance in Helping Member States Develop Effectively Independent and Robust Regulators for Nuclear Installation Safety

Energy Technology Data Exchange (ETDEWEB)

Nicic, A., E-mail: A.Nicic@iaea.org [International Atomic Energy Agency (IAEA), Department of Nuclear Safety and Security, Wagramer Strasse 5, P.O. Box 100, 1400 Vienna (Austria)

2014-10-15

Full text: The International Conference on Topical Issues in Nuclear Installation Safety will be focused on the exchange of information on the latest thinking and advances in the implementation of the concept of Defence-in-Depth (DID) in nuclear installations, and the associated challenges. The focus will be on operating nuclear installations, including nuclear power plants, research reactors and fuel cycle facilities, and on how lessons learned from operating experience and recent events (e.g. the Fukushima Daiichi accident) are used to enhance safety. The implementation of DID covers a number of elements that are directly related to the different states and phases of a nuclear facility. This presentation will discuss the importance of the regulatory body in its oversight role as a cross-cutting element of DID in helping to assure the safety of nuclear installations. Taking note of the numerous challenges in developing an effectively independent and robust regulatory body, the presentation will describe how the IAEA assists Member States in their development of the appropriate regulatory infrastructure and necessary capacity to carry out their regulatory responsibilities – consistent with the IAEA Safety Standards. The presentation will describe the importance of the self-assessment process which serves as a starting point for helping Member States gain an understanding of what support they need and when the support should be provided as they develop into a competent regulatory authority. The presentation will discuss recent improvements in the self-assessment process and related IAEA services in this regard. Once regulatory bodies are established, it is essential that they seek continuous improvement. In this regard, the presentation will describe the IAEA’s assistance provided through the Integrated Regulatory Review Service (IRRS) and recent activities to improve the IRRS, consistent with the IAEA’s Action Plan on Nuclear Safety. (author)

Overview of IAEA Action Plan on Nuclear Safety

International Nuclear Information System (INIS)

Monti, Stefano

2012-01-01

The IAEA Action Plan represents a work programme to strengthen and improve nuclear safety world wide. The plan identifies actions for Member States and the IAEA. Success depends upon: • Cooperation between IAEA, Member States, and other stakeholders; • Availability of appropriate financial resources (MS voluntary contributions)

IAEA symposium on international safeguards. Extended synopses

International Nuclear Information System (INIS)

1997-10-01

The most important subjects treated in 188 papers presented by the participants from member state and IAEA Safeguards Inspectors at the Symposium were as follows: implementation of IAEA safeguards; national support programs to the IAEA safeguards; experiences in application of safeguard monitoring devices; improved methods for verification of plutonium; highly enriched uranium; surveillance of spent fuel storage facilities, reprocessing plants, fuel fabrication plants; excess weapon grade plutonium and other fissile materials

Certified Reference Materials for Radioactivity Measurements in Environmental Samples of Soil and Water: IAEA-444 and IAEA-445

International Nuclear Information System (INIS)

2011-01-01

Reference Materials are an important requirement for any sort of quantitative chemical and radiochemical analysis. Laboratories need them for calibration and quality control throughout their analytical work. The IAEA started to produce reference materials in the early 1960's to meet the needs of the analytical laboratories in its Member States that required reference materials for quality control of their measurements. The initial efforts were focused on the preparation of environmental reference materials containing anthropogenic radionuclides for use by those laboratories employing nuclear analytical techniques. These reference materials were characterized for their radionuclide content through interlaboratory comparison involving a core group of some 10 to 20 specialist laboratories. The success of these early exercises led the IAEA to extend its activities to encompass both terrestrial and marine reference materials containing primordial radionuclides and trace elements. Within the frame of IAEA activities in production and certification of reference materials, this report describes the certification of the IAEA-444 and IAEA-445: soil and water spiked with gamma emitting radionuclides respectively. Details are given on methodologies and data evaluation

IAEA Expands International Cooperation on Small, Medium Sized or Modular Nuclear Reactors

International Nuclear Information System (INIS)

2018-01-01

The International Atomic Energy Agency (IAEA) is launching an effort to expand international cooperation and coordination in the design, development and deployment of small, medium sized or modular reactors (SMRs), among the most promising emerging technologies in nuclear power. Significant advances have been made on SMRs, some of which will use pre-fabricated systems and components to shorten construction schedules and offer greater flexibility and affordability than traditional nuclear power plants. With some 50 SMR concepts at various stages of development around the world, the IAEA is forming a Technical Working Group (TWG) to guide its activities on SMRs and provide a forum for Member States to share information and knowledge, IAEA Deputy Director General Mikhail Chudakov said. “Innovation is crucial for nuclear power to play a key role in decarbonising the energy sector,” Chudakov, who heads the IAEA Department of Nuclear Energy, said at a conference on SMRs in Prague on 15 February. “Many Member States that are operating, expanding, introducing or considering nuclear power are quite keen on the development and deployment of SMRs.” Global interest in SMRs is growing. SMRs have the potential to meet the needs of a wide range of users and to be low carbon replacements for ageing fossil fuel fired power plants. They also display enhanced safety features and are suitable for non-electric applications, such as cooling, heating and water desalination. In addition, SMRs offer options for remote regions with less developed infrastructure and for energy systems that combine nuclear and alternative sources, including renewables.

Comparison of absorbed dose determinations using the IAEA dosimetry protocol and the ferrous sulphate dosimeter

International Nuclear Information System (INIS)

Mattsson, Olof

1988-01-01

In 1985 a comparison of different revised protocols for the dosimetry of high-energy photon and electron beams was published (Mattsson, 1985). The conclusions were that the agreement in absorbed dose to water determined using the different protocols is very good and that the agreement between ionization chamber and ferrous sulphate dosimetry is generally good. For electron beams the differences obtained with the ionization chamber and ferrous sulphate dosimeters were up to about 2%. The influence of the energy and angular distribution of the electron beams on the ionization chamber dosimetry is not fully considered in the dosimetry protocols. The basis for the ionization chamber dosimetry has recently been changed when the Bureau International des Poids et Mesures (BIPM) in 1986 changed the air-kerma standard. The reason was the adaption of the new stopping-power values reported in the ICRU Report No. 37. To achieve consistency in the ionization chamber dosimetry the interaction coefficients and correction factors given in the dosimetry protocols should also be based on the same set of stopping-power values. This is not the case with the protocols included in the comparison made by Mattsson. However, in the international code of practice by the International Atomic Energy Agency (IAEA, 1987) the new stopping-power values have been used. The formalism is the same as in most of the previous protocols. Mattsson et al. (1989) have shown that the differences in the various steps cancel out for the protocols published by NACP (1980) and by IAEA (1987) for cobalt-60 gamma quality. However, it is also of interest to investigate the influence of the new air-kerma standard and the new values on coefficients and factors given in the IAEA protocol for other beam qualities. Therefore, the data given by Mattsson (1985) have been recalculated using the new air-kerma standard and the IAEA protocol

Radionuclide transfer to fruit in the IAEA TRS No. 472

Directory of Open Access Journals (Sweden)

Giosuè S.

2012-04-01

Full Text Available This paper describes the approach taken to present the information on fruits in the IAEA report TRS No. 472, supported by the IAEA-TECDOC-1616, which describes the key transfer processes, concepts and conceptual models regarded as important for dose assessment, as well as relevant parameters for modelling radionuclide transfer in fruits. Information relate to fruit plants grown in agricultural ecosystems of temperate regions. The relative significance of each pathway after release of radionuclides depends upon the radionuclide, the kind of crop, the stage of plant development and the season at time of deposition. Fruit intended as a component of the human diet is borne by plants that are heterogeneous in habits, and morphological and physiological traits. Information on radionuclides in fruit systems has therefore been rationalised by characterising plants in three groups: woody trees, shrubs, and herbaceous plants. Parameter values have been collected from open literature, conference proceedings, institutional reports, books and international databases. Data on root uptake are reported as transfer factor values related to fresh weight, being consumption data for fruits usually given in fresh weight.

Analysis of historical delta values for IAEA/LANL NDA training courses

International Nuclear Information System (INIS)

Geist, William; Santi, Peter; Swinhoe, Martyn; Bonner, Elisa

2009-01-01

The Los Alamos National Laboratory (LANL) supports the International Atomic Energy Agency (IAEA) by providing training for IAEA inspectors in neutron and gamma-ray Nondestructive Assay (NDA) of nuclear material. Since 1980, all new IAEA inspectors attend this two week course at LANL gaining hands-on experience in the application of NDA techniques, procedures and analysis to measure plutonium and uranium nuclear material standards with well known pedigrees. As part of the course the inspectors conduct an inventory verification exercise. This exercise provides inspectors the opportunity to test their abilities in performing verification measurements using the various NDA techniques. For an inspector, the verification of an item is nominally based on whether the measured assay value agrees with the declared value to within three times the historical delta value. The historical delta value represents the average difference between measured and declared values from previous measurements taken on similar material with the same measurement technology. If the measurement falls outside a limit of three times the historical delta value, the declaration is not verified. This paper uses measurement data from five years of IAEA courses to calculate a historical delta for five non-destructive assay methods: Gamma-ray Enrichment, Gamma-ray Plutonium Isotopics, Passive Neutron Coincidence Counting, Active Neutron Coincidence Counting and the Neutron Coincidence Collar. These historical deltas provide information as to the precision and accuracy of these measurement techniques under realistic conditions.

IAEA symposium on international safeguards. Extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

The most important subjects treated in 188 papers presented by the participants from member state and IAEA Safeguards Inspectors at the Symposium were as follows: implementation of IAEA safeguards; national support programs to the IAEA safeguards; experiences in application of safeguard monitoring devices; improved methods for verification of plutonium; highly enriched uranium; surveillance of spent fuel storage facilities, reprocessing plants, fuel fabrication plants; excess weapon grade plutonium and other fissile materials Refs, figs, tabs

The k0-IAEA program

International Nuclear Information System (INIS)

Rossbach, M.; Blaauw, M.; Bacchi, M.A.; Xilei Lin

2007-01-01

New software was developed to assist users of the k 0 -approach in NAA to harmonize their results. The k 0 -IAEA software uses the holistic approach developed at the Delft Interfaculty Reactor Institute and incorporates the latest k 0 data catalogue together with additional information on coincidence and sum peaks, which together are used in the joint evaluation of samples. Multiple irradiations as well as multiple measurements of samples are treated simultaneously. Flux parameter determination as well as efficiency calibrations of detectors are accommodated using a singlemeasurement approach as developed at the Interfaculty Reactor Institute, Delft. The standard Windows software will stimulate the application of the k 0 approach through the free distribution and updates of the program. (author)

IAEA Concludes Follow-up Review of Malaysia Rare Earth Plant IAEA Concludes Follow-up Review of Malaysia Rare Earth Plant

International Nuclear Information System (INIS)

2014-01-01

In its preliminary observations, the follow-up mission found that good progress had been made in implementing the recommendations of the 2011 mission, and noted that the radiological risks of the Lynas plant are low because of the very low level of radioactivity of the materials handled. The team also noted that Malaysia is actively updating its regulations in accordance with the most recent IAEA safety standards. The IAEA team gave some advice for further progress in specific areas. For example: The waste management plan should be based on realistic scenarios including, if considered appropriate, the identification of a final disposal site. Environmental monitoring activities should be optimised to ensure resources are focused on the most important areas, including enhancing monitoring of liquid discharges. The basis of the financial fund to be paid by Lynas for long-term waste management and decommissioning should be communicated more clearly. The AELB and Lynas are encouraged to maintain a proactive approach to relations with the media, public and other stakeholders, on an ongoing basis, to address continuing widespread misconceptions about the plant and radiation issues in general. Rare earths are elements used in many high-technology applications, from mobile phones to wind turbines. Since the ore from which they are refined also usually contains naturally occurring radioactive materials such as thorium or uranium, the process results in very low-level radioactive waste that must be managed safely. The IAEA mission's final report will be submitted to the Malaysian government at the end of October, and will be made public

IAEA's role in nuclear desalination

International Nuclear Information System (INIS)

Khamis, I.; )

2010-01-01

Currently, several Member States have shown interest in the utilization of the nuclear energy for seawater desalination not only because recent studies have demonstrated that nuclear desalination is feasible, but also economical and has been already demonstrated in several countries. Therefore, the article will provide a highlight on sea water desalination using nuclear energy as a potential for a sustainable development around the world and the IAEA role in this regards. Special emphasis is placed on past, present, and future nuclear desalination experience in various IAEA Member States. The International Atomic Energy Agency (IAEA) role could be summarized in facilitating cutting-edge developments in the area of seawater desalination using nuclear energy, and establishing a framework for facilitating activities in Member States through information exchange and provision of technical assistance. (author)

IAEA General Conference begins annual session

International Nuclear Information System (INIS)

2001-01-01

The document gives general information about the opening and the programme of the 45th regular session of the IAEA General Conference (17-21 September 2001, Austria Center Vienna). The conference is attended by ministers and high-level governmental representatives from 132 Member States of the IAEA

IAEA General Conference begins annual session

International Nuclear Information System (INIS)

2000-01-01

The document gives general information about the opening and the programme of the 44th regular session of the IAEA General Conference (18 -22 September 2000, Austria Center Vienna). The conference is attended by ministers and high-level governmental representatives from 130 Member States of the IAEA

Quality assurance measures applicable to IAEA anomaly and discrepancy resolution (ISPO Task D.52). Program for technical assistance to IAEA safeguards

International Nuclear Information System (INIS)

Harms, N.L.; Smith, B.W.

1984-11-01

The International Atomic Energy Agency (IAEA) safeguards program provides assurance to the international community that nations comply with their commitments for the peaceful use of nuclear energy. This assurance is based on the capabilities of the IAEA safeguards program to detect diversion of nuclear material. Anomalies and discrepancies, which occur in the event of a diversion or concealment, are detected as part of the IAEA safeguards program. Anomalies and discrepancies normally result from innocent causes and it is the purpose of the resolution process to determine the significance of them. The IAEA is instituting quality assurance measures for the IAEA inspection process. This paper reviews the anomaly and discrepancy resolution process and describes quality control measures which are the basis for quality assurance. 13 references, 6 tables

Knowledge Management in the IAEA Department of Safeguards

International Nuclear Information System (INIS)

Konecni, S.; Carrillo de Fischer, J.

2016-01-01

Full text: Knowledge Management (KM) is an integral part of the Departmental Quality Management System because knowledge (i.e., the ‘know-how’, ‘know-when’, ‘know-who’, ‘know-why’, etc.) is needed to produce high quality products and services on a daily basis. The ability to continue providing such products and services is challenged each time an experienced staff member leaves the IAEA due to retirement or end of contract and takes with them important job-related knowledge. The most important assets in the International Atomic Energy Agency (IAEA) Department of Safeguards (SG) are people and their knowledge. The Department of Safeguards developed a knowledge management (KM) framework and the corresponding approaches as well as specific guidelines for its implementation. Knowledge retention (KR) is part of knowledge management and focusses on eliminating the risk of losing the critical job-related knowledge by putting in place a systematic knowledge retention plan. Particularly, for knowledge retention, the Safeguards Division of Concepts and Planning (SGCP) developed a model to draw out and capture the critical knowledge and making it available for use by others. This paper describes the knowledge retention model/approach and lessons learned from implementing the knowledge management programme in SG. (author

Overview of the IAEA's activity on ISI qualification

International Nuclear Information System (INIS)

Trampus, P.

2000-01-01

The IAEA Subprogram on Nuclear Power Planning, Implementation and Performance is presented. It's objective is to assist Member States in: planning nuclear power programmes in an integrated manner considering all necessary factors; systematically improving overall performance and competitiveness of NPPs trough entire service life with due regard to safety; applying technological/engineering best practices including QA/QM in all areas of nuclear power utilisation. International working group on life management of NPPs (IWG-LMNPP) has been established in 1975 with 26 Member States and 2 international organizations in order to provide the Director General with advice and opinions and the Member States with information, recommendations and support in life management issues.The technical co-operation program RER/4/020 'Advanced NDT of Primary Circuit Components' is presented.The pilot study is aimed to provide the participating Member States with practical advice how to apply the IAEA's qualification methodology. The target application is Technical Justification for UT of WWER-1000 RPV shell weld (unit 5 of 'Kozloduy NPP). The concept is to simulate the qualification process through assistance to establish qualification for a real NPP component, using real ISI, in a real regulatory environment. Interim results for Bulgaria are reported and further tasks are outlined

Guidelines for the Review of Research Reactor Safety: Revised Edition. Reference Document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

International Nuclear Information System (INIS)

2013-01-01

The Integrated Safety Assessment of Research Reactors (INSARR) is an IAEA safety review service available to Member States with the objective of supporting them in ensuring and enhancing the safety of their research reactors. This service consists of performing a comprehensive peer review and an assessment of the safety of the respective research reactor. The reviews are based on IAEA safety standards and on the provisions of the Code of Conduct on the Safety of Research Reactors. The INSARR can benefit both the operating organizations and the regulatory bodies of the requesting Member States, and can include new research reactors under design or operating research reactors, including those which are under a Project and Supply Agreement with the IAEA. The first IAEA safety evaluation of a research reactor operated by a Member State was completed in October 1959 and involved the Swiss 20 MW DIORIT research reactor. Since then, and in accordance with its programme on research reactor safety, the IAEA has conducted safety review missions in its Member States to enhance the safety of their research reactor facilities through the application of the Code of Conduct on the Safety of Research Reactors and the relevant IAEA safety standards. About 320 missions in 51 Member States were undertaken between 1972 and 2012. The INSARR missions and other limited scope safety review missions are conducted following the guidelines presented in this publication, which is a revision of Guidelines for the Review of Research Reactor Safety (IAEA Services Series No. 1), published in December 1997. This publication details those IAEA safety standards and guidance publications relevant to the safety of research reactors that have been revised or published since 1997. The purpose of this publication is to give guidance on the preparation, implementation, reporting and follow-up of safety review missions. It is also intended to be of assistance to operators and regulators in conducting

IAEA Leads Operational Safety Mission to Rajasthan Atomic Power Station 3 and 4

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) today completed a review of safety practices at Units 3 and 4 of the Rajasthan Atomic Power Station in Rawatbhata. The team noted a series of good practices and made recommendations and suggestions to reinforce safety practices. The IAEA assembled the Operational Safety Review Team (OSART) at the request of the Government of India. Led by the IAEA's Division of Nuclear Installation Safety, the team performed an in-depth operational safety review from 29 October to 14 November 2012. The team was comprised of experts from Canada, Belgium, Finland, Germany, Romania, Slovakia, Slovenia, Sweden and the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Power Plant. The conclusions of the review are based on the IAEA's Safety Standards and good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. The OSART team identified a number of good practices of the plant. These will be shared in due course by the IAEA with the global nuclear industry for consideration. Examples include the following: - The Power Plant's safety culture cultivates a constructive work environment and a sense of accountability among the Power Plant personnel, and gives its staff the opportunity to expand skills and training; - The Power Plant's Public Awareness Programme provides educational opportunities to the local community about nuclear and radiation safety; - The Power Plant has a Management of Training and Authorization system for effective management of training activities; and - The Power Plant uses testing facilities and mockups to improve the quality of maintenance work and to reduce radiation doses. The OSART

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Ed.). Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-06-15

This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6, Regulations for the Safe Transport of Radioactive Material (2012 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Standards Series No. TS-G-1.1 Rev. 1, which was issued in 2008.

IAEA activity related to safety of nuclear desalination

International Nuclear Information System (INIS)

Gasparini, M.

2000-01-01

The nuclear plants for desalination to be built in the future will have to meet the standards of safety required for the best nuclear power plants currently in operation or being designed. The current safety approach, based on the achievement of the fundamental safety functions and defence in depth strategy, has been shown to be a sound foundation for the safety and protection of public health, and gives the plant the capability of dealing with a large variety of sequences, even beyond the design basis. The Department of Nuclear Safety of the IAEA is involved in many activities, the most important of which are to establish safety standards, and to provide various safety services and technical knowledge in many Technical Co-operation assistance projects. The department is also involved in other safety areas, notably in the field of future reactors. The IAEA is carrying out a project on the safety of new generation reactors, including those used for desalination, with the objective of fostering an exchange of information on safety approaches, promoting harmonization among Member States and contributing towards the development and revision of safety standards and guidelines for nuclear power plant design. The safety, regulatory and environmental concerns in nuclear powered desalination are those related directly to nuclear power plants, with due consideration given to the coupling process. The protection of product water against radioactive contamination must be ensured. An effective infrastructure, including appropriate training, a legal framework and regulatory regime, is a prerequisite to considering use of nuclear power for desalination plants, also in those countries with limited industrial infrastructures and little experience in nuclear technology or safety. (author)

IAEA response assistance network. Incident and Emergency Centre. Emergency preparedness and response. Date effective: 1 May 2006

International Nuclear Information System (INIS)

2006-03-01

This publication is intended to serve as a tool for supporting the provision of international assistance in the case of nuclear or radiological incident or emergency, cooperation between States, their Competent Authorities and the IAEA, and harmonization of response capabilities of States offering assistance. The publication is issued under the authority of the Director General of the IAEA: (1) under the auspices of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the Assistance Convention) [1], to promote, facilitate and support cooperation between States Parties to coordinate and/or provide assistance to a State Party and/or Member State; and (2) in the case of an incident or emergency, as statutory functions, to provide for the application of its safety standards, upon request by a Member State, and to act as an intermediary for the purposes of securing the performance of services or the supplying of materials, equipment or facilities by one Member State for another. The publication sets out the following: a) the RANET concept and the organizational structure for providing assistance; b) functions, responsibilities and activities within the RANET; c) the RANET response operations and arrangements needed for preparedness; and d) the prerequisites for RANET membership and conditions of registration. The RANET is divided into four sections. After the introduction in Section 1, the RANET concept, objectives and scope are described in Section 2. Section 3 presents the concept of operations of the RANET and Section 4 describes expected tasks, capabilities and resources. In addition, EPR-RANET (2006) has three supporting documents, which are issued separately, as follows: 1. Assistance Action Plans with samples of Assistance Action Plans for providing international assistance. 2. Registry with the details of the registry and instructions on how to register national assistance capabilities for the RANET. 3. Technical Guidelines

10 CFR 75.8 - IAEA inspections.

Science.gov (United States)

2010-01-01

... NRC Operations Center (commercial telephone number 301-816-5100). (d) Each applicant, licensee, or... surveillance; and (6) Perform other measures requested by the IAEA and approved by the NRC. (f) Each applicant... measurement and surveillance; (ii) Enabling the IAEA to apply its seals and other identifying and tamper...

IAEA Nobel Peace Prize cancer and nutrition fund

International Nuclear Information System (INIS)

Kinley, D. III

2006-05-01

The Norwegian Nobel Committee awarded the 2005 Nobel Peace Prize to the IAEA and Director General ElBaradei in equal shares. The IAEA and its Director General won the 2005 Peace Prize for their efforts to prevent nuclear energy from being used for military purposes and to ensure that nuclear energy for peaceful purposes is used in the safest possible way. The IAEA Board of Governors subsequently decided that the IAEA's share of the prestigious prize would be used to create a special fund for fellowships and training to improve cancer control and childhood nutrition in the developing world. This fund is known as the 'IAEA Nobel Peace Prize Cancer and Nutrition Fund'. The money will be dedicated to enhancing human resources in developing regions of the world for improved cancer control and childhood nutrition. In the area of cancer control, the money will be spent on establishing regional cancer training institutes for the training of new doctors, medical physicists and technologists in radiation oncology to improve cancer treatment and care, as part of the IAEA's Programme of Action for Cancer Therapy (PACT). In the realm of nutrition, the focus of the Fund will be on capacity building in the use of nuclear techniques to develop interventions to contribute to improved nutrition and health for children in the developing world. Fund-supported fellowship awards will target young professionals, especially women, from Member States, through the IAEA's Technical Cooperation (TC) Programme. Alongside such awards, regional events will be organized in Africa, Asia and Latin America in cancer control and nutrition during 2006. The IAEA Secretariat is encouraging Member States and donors to contribute to the IAEA Nobel Peace Prize Cancer and Nutrition Fund by providing additional resources, in cash and in-kind

IAEA receives Iraq's nuclear-related declaration

International Nuclear Information System (INIS)

2002-01-01

Full text: The Director General of the International Atomic Energy Agency, Mohamed ElBaradei, announced that the IAEA received this evening, Sunday, 8 December 2002, at its Headquarters in Vienna, an approximately 2400 page declaration on Iraq's nuclear programme. The declaration consists of about 2100 pages in English and 300 pages in Arabic. The declaration was submitted by the Government of Iraq in response to paragraph 3 of Security Council resolution 1441 (8 November 2002), which requires Iraq to provide to UNMOVIC, the IAEA and to the Security Council, not later than 30 days of the date of that resolution, with 'currently accurate, full, and complete declaration of all aspects of its programmes to develop chemical, biological, and nuclear weapons, ballistic missiles, and other delivery systems... as well as all other chemical, biological, and nuclear programmes, including any which it claims are for purposes not related to weapon production or material'. 'The IAEA will immediately begin to assess this important new document,' said Mr. ElBaradei, 'including the painstaking and systematic cross-checking of the information provided by Iraq against information which the IAEA already has, information that it expects to receive from other Member States, as contemplated in resolution 1441, and results of past and present Agency verification activities.' Complete assessment of the declaration will be time consuming, particularly in light of the need to translate the 300 pages of Arabic text into English. However, the IAEA expects to be able to provide a preliminary analysis of the document to the Security Council within the next ten days, with a fuller assessment to be provided when it reports to the Council at the end of January. (IAEA)

European Commission and IAEA Celebrate 30 Years Co-operation on Nuclear Safeguards

International Nuclear Information System (INIS)

2011-01-01

reprocessing plant in Japan and is now being installed in other facilities in Europe - Secure Sealing: During the last 30 years, the Seal and Identification Laboratory (SILab) of the JRC developed and produced ultrasonic bolt seals requested by the IAEA in order to seal underwater nuclear spent fuel assemblies. In 2011, after a training session at JRC in Ispra, Italy, a joint team of inspectors from the IAEA and EURATOM Safeguards and the European Commission's Directorate-General for Energy successfully sealed the first nuclear fuel bundles produced by the Cernavoda II reactor in Romania. Joint Research Centre (JRC): The JRC is the European Commission's in-house science service. Its mission is to provide customer-driven scientific and technical support for the conception, development, implementation and monitoring of European Union policies. The JRC serves the common interest of the Member States, while being independent of special interests, whether private or national. International Atomic Energy Agency (IAEA): The IAEA serves as the world's foremost intergovernmental forum for scientific and technical co-operation in the peaceful use of nuclear technology. Established as an autonomous organization under the United Nations (UN) in 1957, the IAEA carries out programmes to maximize the useful contribution of nuclear technology to society while verifying its peaceful use. (IAEA)

Calculation of pre and post-test of the third. proposed standard problem exercise, for the PMK-NVH-IAEA experiment using the RELAP4/MOD5 and RELAP5/MOD1

International Nuclear Information System (INIS)

Neves Conti, T. das; Sabundjian, G.; Oliveira Neto, J.M. de

1992-01-01

The results of RELAP4/MOD5 and RELAP5/MOD1 modeling tests against the steam generator tube rupture experiments performed at PMK-NVH Experimental Loop Facility (IAEA-Standard Problem Exercise-3) are presented in the report. The pre and post-test results, when compared against the experimental data were satisfactorily good, except a discrepancy in the steam-generator relief valve opening time. (author)

IAEA advisory group meeting on nuclear structure and decay data. IAEA, Vienna 21-25 April 1980

International Nuclear Information System (INIS)

Lorenz, A.

1980-10-01

The IAEA Nuclear Data Section convened the fourth meeting of the international nuclear structure and decay data network at IAEA Headquarters in Vienna, Austria, from 21-25 April 1980. The meeting was attended by 23 Scientists from 11 Member States and 2 international organizations, concerned with the compilation, evaluation, and dissemination of nuclear structure and decay data. (author)

The IAEA '97 Pacific Ocean expedition

International Nuclear Information System (INIS)

Povinec, P.P.; Huynh-Ngoc, L.; Liong Wee Kwong, L.

1999-01-01

The International Atomic Energy Agency's Marine Environment Laboratory (IAEA-MEL) started in 1995 a five-year project 'Research on World-wide Marine Radioactivity', generously supported by the Government of Japan. In the framework of the project, IAEA-MEL conducted the 'IAEA '97 Pacific Ocean Expedition' to the NW Pacific Ocean from 21 October to 20 November, 1997. The objectives of the expedition were to provide new data on the current marine radioactivity in order to compare them with data sets obtained during national and international surveys at sites used for radioactive waste dumping or nuclear bomb testing in the NW Pacific Ocean and its marginal seas

Artificial radioactivity in the environmental samples as IAEA reference materials

International Nuclear Information System (INIS)

Salagean, M.; Pantelica, A.

1998-01-01

Radioactivity levels of 110m Ag, 241 Am, 60 Co, 134 Cs, 137 Cs, 106 Ru, 125 Sb in some biological and environmental materials have been determined by gamma-ray spectrometry in the frame of 15 intercomparison runs organized by IAEA during 1986-1995. The investigated materials were polluted by various nuclear activities, as follows: 1. Nuclear experiments: IAEA-367, sediment collected in 1982 at the Enewetak Atoll (Marshall Islands in the Pacific Ocean). This atoll was used by the USA during 1948-1958 to test nuclear devices; IAEA-368, sediment collected in June 1989 from the Pacific Ocean at the Mururoa Atoll. Since 1966 this atoll has been used by France to test different nuclear devices. 2. Nuclear installations: IAEA-134, cockle flesh of Cardium edule collected in March 1991 from the Irish Sea (Morecambe Bay), England, about 45 km S-E of Sellafield radioactive discharge; IAEA-135, sediment collected in July 1991 in Lune Estuary-England. This area is influenced by the radioactive discharges of the nuclear installations of Sellafield; IAEA-326, soil collected in 1990 in the region of Kursk Atomic Power Plant (Russia). 3. Nuclear accidents (Chernobyl): IAEA-306, sediment collected in the Baltic Sea during October-November 1986; IAEA-307, seaplant Posidonia oceanica, collected in October 1986 in Mediterranean Sea along the shore, in the vicinity of the Principality of Monaco; IAEA-308, mixed seaweeds collected in October 1986 in Mediterranean Sea along the shore, in the vicinity of the Principality of Monaco; IAEA-156, clover collected during the summer harvest 1986 in Austria; IAEA-321, milk powder collected in autumn 1987 from a processing plant in Europe; IAEA-352, tuna fish flesh collected in April 1988 in the Western Mediterranean Sea; IAEA-373, grass collected from Kiev region during the summer harvest 1990; IAEA-375, soil collected in July 1990 from Brjansk region, Russia; IAEA-300, sediment collected in July 1992 in Bothnian Sea (Baltic Sea). 4

IAEA launches a pictorial history book of 'Atoms for Peace' [196 pp.; 850 figs; 2007; ISBN 978-103807-4; 50 Euro

International Nuclear Information System (INIS)

2007-01-01

Full text: To commemorate its first 50 years, the International Atomic Energy Agency is today launching a photographic history of the organization and its work. A large volume, elegantly produced, it offers an overview of the Agency that is both attractive and educational. The book explores in pictures the balance between the IAEA's work as a nuclear watchdog and rigorous advocate for safety and security and its mission in helping developing countries use advanced science for humanitarian benefit. Issued at a time of unprecedented international interest in the Agency, it addresses the fundamental concepts that underlie the work of the IAEA and its 'Atoms for Peace' mission. It also describes the historical evolution of the IAEA, illustrating the successes and challenges that have shaped the organization over the past half century. Notable milestones covered include US President Eisenhower's Atoms for Peace speech, the establishment of safeguards regimes, the international response to the Chernobyl accident and the awarding of the Nobel Peace Prize in 2005. Ongoing efforts, in fields ranging from sustainable energy production to human health and agricultural productivity, further detail the diversity and complexity of the IAEA's contribution - as IAEA Director General Mohamed ElBaradei explains in the foreword - to 'the betterment of the human family.' (IAEA)

IAEA Newsbriefs. V. 14, no. 4(85). Oct-Nov 1999

International Nuclear Information System (INIS)

1999-01-01

This issue gives brief information on the following topics: the new IAEA Board of Governors, conclusions of the 1999 IAEA General Conference, the return of the IAEA fact-finding team from Japan, future energy and nuclear power, talks on future IAEA verification of ex-weapon material, the IAEA and Y2K (steps against the bug intensify), African partnership for technology transfer extended, strengthened safeguards system (status of additional protocols), and other short information

IAEA/NEA Fuel Incident Notification and Analysis System (FINAS) guidelines

International Nuclear Information System (INIS)

2006-01-01

The Fuel Incident Notification and Analysis System (FINAS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development (OECD/NEA). The fundamental objective of FINAS is to contribute to improving the safety of fuel cycle facilities, which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance, which occur at these facilities. The purpose of these guidelines, which supersede the previous NEA FINAS guidelines is to describe the system and to give users the necessary background and guidance to enable them to produce FINAS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating FCFs. These guidelines have been jointly developed and approved by the NEA/IAEA

Common Risk Target for severe accidents of nuclear power plants based on IAEA INES scale

International Nuclear Information System (INIS)

Vitázková, Jiřina; Cazzoli, Errico

2013-01-01

The IAEA has repeatedly recommended that the nuclear community should arrive at a common understanding and definition of safety goals for severe accidents in nuclear power plants. The recommendation has only found partial answers, despite the numerous working groups and forums devoted to this effort. The most widely accepted definition of goals is based on the concept of Large (Early) Release Frequencies (L(E)RF) and its derivatives, a surrogate concept derived from results of Probabilistic Safety Assessments (PSAs) which was first introduced in the USA almost twenty years ago and much later accepted by the USNRC for risk informed decision making, but not for safety demonstrations. Other types of Safety Goals have been adopted by some nuclear authorities, but the main drawback of all current definitions is that they may apply only to LWRs. The lack of unifying safety/risk parameter throughout of PSAs worldwide is the basis of the present work, and an attempt is made to arrive at the definition of a Risk Target for severe accidents in NPPs, consistent with the IAEA definitions having a technical basis, which can be adopted without modifications for Generation IV power plants. The proposal of Common Risk Target in this work represents an attempt to define a Common Risk Target based on technical reasoning, reflecting IAEA definitions as well as harmonization requirements raised by the whole European Community in various OECD, ASAMPSA2 and SARNET (Guentay et al., 2006) conclusions and Council Directive of The European Union (Community Framework, 2009) as well as lastly performed stress tests of nuclear power plants throughout the Europe (Peer Review Report, 2012). The basic concept of CRT was first introduced and developed within the European project ASAMPSA2 by the authors of this article and was accepted by majority of world PSA experts participating in final evaluation and survey of the project (Guentay, 2011). In the proposed Risk Target concept an innovative

Common Risk Target for severe accidents of nuclear power plants based on IAEA INES scale

Energy Technology Data Exchange (ETDEWEB)

Vitázková, Jiřina, E-mail: jirina@snus.sk [Vitázková-Vitty, Sládkovičova 24, 900 28 Ivanka pri Dunaji (Slovakia); Cazzoli, Errico, E-mail: erik.cazzoli@gmx.net [Cazzoli Consulting, Wiesenweg 14, CH-5415 Nussbaumen (Switzerland)

2013-09-15

The IAEA has repeatedly recommended that the nuclear community should arrive at a common understanding and definition of safety goals for severe accidents in nuclear power plants. The recommendation has only found partial answers, despite the numerous working groups and forums devoted to this effort. The most widely accepted definition of goals is based on the concept of Large (Early) Release Frequencies (L(E)RF) and its derivatives, a surrogate concept derived from results of Probabilistic Safety Assessments (PSAs) which was first introduced in the USA almost twenty years ago and much later accepted by the USNRC for risk informed decision making, but not for safety demonstrations. Other types of Safety Goals have been adopted by some nuclear authorities, but the main drawback of all current definitions is that they may apply only to LWRs. The lack of unifying safety/risk parameter throughout of PSAs worldwide is the basis of the present work, and an attempt is made to arrive at the definition of a Risk Target for severe accidents in NPPs, consistent with the IAEA definitions having a technical basis, which can be adopted without modifications for Generation IV power plants. The proposal of Common Risk Target in this work represents an attempt to define a Common Risk Target based on technical reasoning, reflecting IAEA definitions as well as harmonization requirements raised by the whole European Community in various OECD, ASAMPSA2 and SARNET (Guentay et al., 2006) conclusions and Council Directive of The European Union (Community Framework, 2009) as well as lastly performed stress tests of nuclear power plants throughout the Europe (Peer Review Report, 2012). The basic concept of CRT was first introduced and developed within the European project ASAMPSA2 by the authors of this article and was accepted by majority of world PSA experts participating in final evaluation and survey of the project (Guentay, 2011). In the proposed Risk Target concept an innovative

Absorbed dose to water comparison between NE 2561 and NE 2671 chambers using IAEA, HPA and NACP protocols for gamma ray beam

International Nuclear Information System (INIS)

Mohd Taufik Dolah; Noriah Mod Ali; Taiman Kadni

2002-01-01

The aim of this study to evaluate the performance of NE 2571 chamber in comparison with NE 2561 chamber in determination of the absorbed dose to water in gamma ray beam. In this study NE 2561 is taking as a reference standard chamber while NE 2571 as a working standard. Irradiation of chamber (alternately) was performed at a reference depth, 5 cm, inside the IAEA water phantom. Both chambers were exposed to 13 difference exposures of gamma rays. The values of absorbed dose to water were then determined using IAEA, HPA and NACP protocols. Deviations of absorbed dose determined by NE 2561 and NE 2571 were calculated for each protocol. result obtained in terms of [protocol, μ (mean deviation) ± σ s e (standard error)] were (IAEA, 1.12 ± 0.04], [HPA, 0.09 ± 0.04], and [NCP, 0.09 ± 0.04]. It can be concluded that NE 2571 shown acceptable performance as it is within acceptable limit ± 3%. (Author)

Tracking Nutritional Progress: IAEA Capacity Building Programmes

International Nuclear Information System (INIS)

Slater, Christine

2014-01-01

Kuwait: The IAEA has helped to establish a body composition assessment suite at the Kuwait Institute for Scientific Research. Facilities include an isotope ratio mass spectrometer for analysis of deuterium and oxygen-18 enrichment, and dual energy X ray absorptiometry for assessment of bone mineral content. Botswana: The IAEA has helped to establish facilities for analysis of deuterium enrichment by Fourier transform infrared (FTIR) spectrometry at the National Food Technology Research Centre (NFTRC). Ecuador: Through national and regional technical cooperation projects, the IAEA has helped to establish facilities for analysis of deuterium enrichment by FTIR spectrometry in 17 Latin American countries, including Ecuador. Costa Rica: With the help of the IAEA, the University of Costa Rica has established a laboratory for the assessment of body composition using deuterium dilution techniques

IAEA Newsbriefs. V. 15, no. 1(86). Jan-Feb 2000

International Nuclear Information System (INIS)

2000-01-01

This issue gives brief information on the following topics: the review of the 2001 draft budget, the return of the IAEA safeguards inspectors from Iraq, the strengthened safeguards system including the signature status of additional protocols as of February 2000, the nomination of the former IAEA Director General H. Blix as head of the new monitoring commission for Iraq, recent statements of the IAEA Director General, the sixth NPT review conference which will open in April 2000, IAEA symposia and seminars in the year 2000, states joining international conventions in nuclear fields, the industry forum convened by the IAEA on nuclear energy issues, cooperation of states against the Y2K problem, IAEA strategy to 2005, sharing lessons from Tokaimura accident, in memoriam of the former IAEA Director General Sigvard Eklund, and other short information

IAEA Assistance on Decommissioning of Small Facilities with Limited Resources

International Nuclear Information System (INIS)

Batandjieva, B.; Warnecke, E.

2008-01-01

The number of facilities reaching their lifetime is increasing and drawing the attention of operators, regulators, public and other interested parties (potential users of the site after decommissioning) on the importance of adequate planning, funding and implementation of decommissioning activities in compliance with regulatory requirements and criteria. Specific attention is required for small facilities that have been used for research purposes and in most cases state owned by and dependent on state funding. With the current tendency for expansion of the nuclear industry such small facilities could become less of importance for the operators which can increase the probability that these facilities become abandoned, hazardous and imposing undue burden to future generations. This concern is more related to countries with limited human and financial resources at the operating organizations and the regulatory body. The International Atomic Energy Agency (IAEA) has been working on the; (i) establishment of internationally recognized safety standards on decommissioning and (ii) providing Member States with assistance on the application of these standards. The recent international conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Practices (Athens, Greece, 2006) has demonstrated that the set of IAEA standards is almost complete and that the International Action Plan on Decommissioning (2004), that is addressing decommissioning of small facilities, is being successfully implemented. However the need for further assistance on decommissioning of small facilities in countries with limited resources was also recognized and the Agency is planning its future work in this field. The IAEA also addresses the needs of small nuclear countries that have only a limited number of nuclear facilities, e.g. a research reactor, in its R esearch Reactor Decommissioning Demonstration Project (R 2 D 2 P. The Philippine Research Reactor

IAEA Activities on Education and training in Radiation and Waste Safety: Strategic approach for a sustainable system

International Nuclear Information System (INIS)

Marabit, K.; Sadagopan, G.

2003-01-01

The statutory safety functions of the International Atomic Energy(IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place, enabling the Government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. the IAEA education and training activities follow the resolutions of its General Conference and reflect the latest IAEA standards and guidance. Several General Conference resolutions have emphasized the importance of education and training (e. g. GC(XXXV)/RES/552 in 1991; GC(XXXVI)/RES/584 in 1992; GC(43)/RES/13 in 1999 and more recently GC(44)/RES/13 in 2000). In response to GC(44)/RES/13, the IAEA prepared a Strategic Approach to Education and Training in Radiation and Waste Safety (Strategy on Education and Training) aiming at establishing, by 2010, sustainable education and training programmes in its Member States. This Strategy was endorsed by the General Conference resolution GC(45)/RES/10C that, inter alia, urged the Secretariat to implement the Strategy on Education and Training, and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. A technical meeting was held in Vienna in March 2002 and concluded with an action plan for implementing the strategy up to 2010, the immediate action being the formation of a Steering Committee by the middle of 2002. This Steering Committee has the general remit to advise on the development and implementation of the strategy, as well as monitoring its progress. The first technical meeting of the Steering Committee took place on 25

Japanese contributions to IAEA INTOR workshop, phase two A, part 2, chapter VI: maintainability

International Nuclear Information System (INIS)

Tomabechi, Ken; Iida, Hiromasa; Honda, Tsutomu

1985-07-01

This report corresponds to Chapter VI of Japanese contribution report to IAEA INTOR Workshop, Phase Two A, Part 2. In this report, we have compared two different reactor concepts, one is based on the personnel access concept where the personnel access is possible to the outside of the torus for maintenance one day after shutdown and the other where the personnel access is not necessary and maintenance is performed in full-remote manner. The results are described from various view points such as reactor configuration, tritium confinement, safety, shielding, maintenance scenario and cost. Data base assessments of maintenance equipment are also reported. (author)

Recruitment of U.S. citizens for vacancies in IAEA Safeguards

International Nuclear Information System (INIS)

Pepper, S.E.; Decaro, D.; Williams, G.; Carelli, J.; Assur, M.

1999-01-01

The International Atomic Energy Agency (IAEA) relies on its member states to assist with recruiting qualified individuals for positions within the IAEA's secretariat. It is important that persons within and outside the US nuclear and safeguards industries become aware of career opportunities available at the IAEA, and informed about important vacancies. The IAEA has established an impressive web page to advertise opportunities for employment. However, additional effort is necessary to ensure that there is sufficient awareness in the US of these opportunities, and assistance for persons interested in taking positions at the IAEA. In 1998, the Subgroup on Safeguards Technical Support (SSTS) approved a special task under the US Support Program to IAEA Safeguards (USSP) for improving US efforts to identify qualified candidates for vacancies in IAEA's Department of Safeguards. The International Safeguards Project Office (ISPO) developed a plan that includes increased advertising, development of a web page to support US recruitment efforts, feedback from the US Mission in Vienna, and interaction with other recruitment services provided by US professional organizations. The main purpose of this effort is to educate US citizens about opportunities at the IAEA so that qualified candidates can be identified for the IAEA's consideration

The IAEA's safeguards systems. Ready for the 21st century

International Nuclear Information System (INIS)

1998-01-01

The publication reviews the IAEA's safeguards system, answering the following questions: What is being done to halt the further spread of nuclear weapons? Why are IAEA Safeguards important? what assurances do safeguards seek to provide? How are safeguards agreements implemented? What specific challenges have there been for IAEA verification? Can the IAEA prevent the diversion of declared Material? How has the safeguards system been strengthened? How much do safeguards cost? What is the future of IAEA verification? (author)

The IAEA's safeguards system. Ready for the 21st century

International Nuclear Information System (INIS)

1997-09-01

The publication reviews the IAEA's safeguards system, answering the following questions: What is being done to halt the further spread of nuclear weapons? Why are IAEA Safeguards important? What assurances do safeguards seek to provide? How are safeguards agreements implemented? What specific challenges have there been for IAEA verification? Can the IAEA prevent the diversion of declared Material? How has the safeguards system been strengthened? How much do safeguards cost? What is the future of IAEA verification?

Radiation safety - an IAEA perspective

International Nuclear Information System (INIS)

Persson, L.

1993-01-01

The activities of the IAEA relating to radiation safety cover: The preparation of International Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources - it is expected that the new Basic Safety Standards will be adopted by the sponsoring organizations in 1994. The radiological consequences of the Chernobyl accident: the thyroid cancer controversy - the hypothesis that must be tested is whether the reported increased incidence of thyroid cancer due to exposure to radioactive iodine released in the Chernobyl accident, and there are several questions that must be answered before a firm conclusion can be reached. Emergency Response Services (ERS): In March 1993, at the request of Viet Nam, which invoked the Energency Assistance Convention, a medical team organized by the IAEA went to Hanoi and assisted in arranging for an overexposed person to be transferred from Viet Nam to Paris for specialized medical treatment. In April 1993, the ERS was used to inform Member States of the consequences of an explosion at the Tomsk 7 fuel reprocessing plant in Siberia, Russia, which caused a radiation leak. Reassessing the long range transport of radioactive material through the environment: Data from the Chernobyl accident have been used for model validation in the Atmospheric Transport Model Evaluation Study (ATMES). A follow-up programme, the European Tracer Experiment (ETEX) with experimental studies of long range atmospheric movements over Europe has been established in order to increase knowledge and prediction capability. As part of the programme, a non-toxic atmospheric tracer will be released under suitable conditions in 1994. The Radiation Protection Advisory Teams Service (RAPAT): In many of the developing countries visited, the lack of an adequate infrastructure for radiation protection is the main obstacle to improved radiation protection. Strengthening radiation and nuclear safety infrastructures in successor states of the USSR: The

The role of the IAEA codes of practice in the radiation dosimetry dissemination chain

International Nuclear Information System (INIS)

Andreo, P.

2002-01-01

Full text: More than 30 years ago the International Atomic Energy Agency (IAEA) published on behalf of IAEA, WHO and PAHO its first Code of Practice (CoP) for radiotherapy dosimetry, TRS-110. Aimed at kV x-rays, 60 Co and 137 Cs therapy in developing countries, and based on roentgens and rads, 'old book' readers will still find interesting practical recommendations like QA procedures that include radiographs of the ionization chamber to check that the internal electrode construction has not moved. TRS-110 was also the first and only CoP with the distinction of including the name of the author in its cover, John B Massey, recognizing that IAEA acted solely as a publisher. For the following almost 20 years IAEA dosimetry activities have prioritized the development of a Network of Secondary Standard Dosimetry Laboratories (SSDLs). In addition to disseminating traceable radiation metrology standards, in some countries the SSDLs have played the important role of compensating the lack of qualified medical physicists. The balance between radiation metrology and medical physics has now shifted towards the first area and the IAEA recommends that SSDLs should not perform the duties of medical physicists except in dire situations. During this long period, there were no updates of TRS-110 or a new IAEA CoP published, even if different generations of national dosimetry protocols had emerged. The absence of IAEA recommendations favoured the arbitrary use of such national protocols, mostly issued in UK and USA, with the result that multiple protocols were used within a given country and there were no practical links between medical physics and SSDLs except for detector calibrations. The publication in 1987 of the TRS-277 Code of Practice established a quantum leap with regard to the Agency's role in harmonizing international radiotherapy dosimetry. A new generation of N K -based national protocols had emerged in the early eighties, and the authors of TRS-277 were chosen among

IAEA program for the preparation of safety codes and guides for nuclear power plants

International Nuclear Information System (INIS)

1975-01-01

On the 13th of September, 1974, the IAEA Governors' Council has given its consent to the programme for the establishment of safety codes and guides (annex VII to IAEA document G.C. (XVIII/526)). The programme envisages the establishment of one code of practice for each of the issues governmental organization, siting, design, operation and quality assurance and also of about 50 safety guides between 1975 and 1980. These codes will contain the minimum requirements for the safety of the nuclear power stations, their systems and components. The guides will recommend methods to achieve the aims stated in the codes. It is the purpose of these IAEA activities to provide recommendations and guiding rules which may serve as standards for the assessment of the safety of nuclear power stations for all nations which may become participants in the peaceful use of nuclear energy within the next few years. (orig./AK) [de

IAEA Newsbriefs. V. 15, no. 4(89). Oct-Nov 2000

International Nuclear Information System (INIS)

2000-01-01

This issue gives information about the following topics: IAEA 2000 General Conference; IAEA Board for 2000-2001; Scientific forum on radioactive waste management: turning options into solutions; the Director General's statement to the General Conference; National case studies on nuclear power and sustainable development; Progress toward IAEA verification under Trilateral Initiative with Russia and the USA; Uranium production and the environment; IAEA publications; States joining international conventions in nuclear fields; Upcoming IAEA international symposia and seminars, and other short information

IAEA Newsbriefs. V. 15, no. 4(89). Oct-Nov 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

This issue gives information about the following topics: IAEA 2000 General Conference; IAEA Board for 2000-2001; Scientific forum on radioactive waste management: turning options into solutions; the Director General's statement to the General Conference; National case studies on nuclear power and sustainable development; Progress toward IAEA verification under Trilateral Initiative with Russia and the USA; Uranium production and the environment; IAEA publications; States joining international conventions in nuclear fields; Upcoming IAEA international symposia and seminars, and other short information.

A technical analysis of the IAEA nuclear safeguards

International Nuclear Information System (INIS)

Yoon, J. W.

1998-01-01

In the post-Cold War era, the threats of horizontal nuclear proliferation emerge as the forefront security issue while the nuclear arms races among existing nuclear weapon states reduce to a remarkable extent. In this context, there arises lots of research attention to the IAEA nuclear safeguards which have been viewed as the core of international monitoring on the clandestine nuclear activities of potential proliferators. However, previous attention tended to highlight the political aspects of the IAEA nuclear safeguards, centering on the possibilities and limitations of the IAEA's inspection authority. In contrast, this paper purports to focus on the technical aspects of the IAEA nuclear safeguards, so it can show the intrinsic problems of those safeguards in stemming the proliferation of nuclear weapons. This paper mainly deals with the technical objectives and options of the IAEA nuclear safeguards, the technical indices of clandestine nuclear activities, and some measures to improve the efficacy of the IAEA nuclear safeguards. Hopefully, this paper is expected to lead us to approach the issue of the North Korean nuclear transparency from the technical perspective as well as the political one

IAEA inspection team conducting investigation in South Korea

International Nuclear Information System (INIS)

2004-01-01

Full text: On 23 August 2004, during discussions about the initial declarations of the Republic of Korea (ROK) under the Additional Protocol to its Safeguards Agreement, the ROK informed the IAEA that it had enriched nuclear material in the course of atomic vapour laser isotope separation (AVLIS) experiments that had not been declared to the IAEA. The ROK informed the IAEA that these experiments had been on a laboratory scale and involved the production of only milligram quantities of enriched uranium. According to the ROK, these activities were carried out without the Government's knowledge at a nuclear site in Korea in 2000, and that the activities had been terminated. Following receipt of this information, the IAEA dispatched a team of inspectors, headed by the Director of the Safeguards Operations Division responsible for the ROK, to investigate further all relevant aspects of this matter. The inspectors will report to the Director General upon their return to Vienna early next week. The Director General will be informing the Board of Governors of the IAEA's initial findings at the next meeting of the Board of Governors beginning on 13 September 2004. (IAEA)

IAEA Completes Safety Review at Czech Nuclear Power Plant

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts, led by the International Atomic Energy Agency (IAEA), today completed a review of safety practices at Temelin Nuclear Power Station in the Czech Republic. The team highlighted the Power Plant's good practices and also recommended improvements to some safety measures. At the request of the Government of the Czech Republic, the IAEA assembled a team of nuclear installation safety experts to send an Operational Safety Review Team (OSART) to the Power Plant, and the mission was conducted from 5 to 22 November 2012. The team was comprised of experts from Brazil, Hungary, Slovakia, South Africa, Sweden, Ukraine and the United Kingdom. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the Plant's overall safety status. The team at Temelin conducted an in-depth review of the functions essential to the safe operation of the Power Plant, which are under the responsibility of the site's management. The review covered the areas of management, organization and administration; operations; maintenance; technical support; operating experience; radiation protection; chemistry; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of potential application elsewhere. Examples include the following: - The Power Plant has adopted effective computer software to improve the efficiency of the plant to prepare and isolate equipment for maintenance; - The Power Plant undertakes measures to control precisely the chemical parameters that limit corrosion in the reactor's coolant system, which in turn reduce radiation exposure to the workforce; and - The Temelin

IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objectives of the technical meeting were to: • exchange information between the Member States/International Organizations on national and international initiatives addressing knowledge preservation and data retrieval/collection in the field of fast neutron systems; • present and discuss the Member States’/International Organizations’ policies and conditions for releasing to the IAEA both publicly available and confidential information on fast neutron systems; • collect data on fast neutron systems provided by participating Member States/International Organizations and encourage participants to contribute in data collection; • provide recommendations for further IAEA initiatives in the field of fast reactor knowledge preservation

IAEA education and training in radiation protection, transport and waste safety-status and new developments for sustainability

International Nuclear Information System (INIS)

Sadagopan, G.; Mrabit, K.; Wheatley, J.

2008-01-01

IAEA 's education and training activities in radiation, transport and waste safety follow the IAEA vision, strategy and resolutions of its annual General Conferences and reflect the latest IAEA standards and guidance. IAEA prepared a Strategic Approach to Education and Training in Radiation and Waste Safety (Strategy on Education and Training) aiming at establishing, by 2010, sustainable education and training programmes in Member States, which was endorsed by the GC(45)/RES/10C in 2001. In implementing the strategy, IAEA is organising training events at the regional level and assisting the Member States at the national level by providing them the exemplary quality of training material developed at the IAEA. This work will continue ensuring its completeness in all areas of radiation safety. An Inter Centre Network between the Agency and regional, collaborating national training centres is established to facilitate information exchange, improve communication and dissemination of training material. There is a challenge to enhance the technical capability of the Member States to reach sustainability. This is intended through organising number of Train the Trainers events to develop a pool of qualified trainers. The new developments include establishing E-learning, developing a syllabus for training of Radiation Protection Officers and training materials, information materials for radiation workers. These are aimed at assisting Member States attain self sustainability. (author)

The IAEA programme of action for cancer therapy

International Nuclear Information System (INIS)

Oliver, L. D.

2007-01-01

Full text: The International Atomic Energy Agency (IAEA) was awarded the Nobel Peace Prize on 10 December 2005. To acknowledge receiving this prestigious award, the IAEA arranged three special workshops in the regions of Asia, Africa and South America. These special events brought together high-ranking delegates from IAEA member countries within their regions. The theme of the workshop was on human resources development in radiation oncology in the context mmcer control programs. This paper presents information on the world cancer incidence provided the International Agency for Research on Cancer (IARC). Details of the IAEA Programme of Action for Cancer Therapy (PACT) 2 are also presented.

Scientific forum - The future role of the IAEA

International Nuclear Information System (INIS)

2008-01-01

The nature and scope of the IAEA's programme to 2020 and beyond was the theme of the Scientific Forum 2008. The theme was chosen to reflect on the challenges and issues facing the IAEA and the resources and requirements needed to meet them. During the opening speech, IAEA Director General Mohamed ElBaradei described the magnitude of the issues lying ahead in the areas of nuclear safeguards, security, safety, and peaceful development. 'We need to look at the big picture, where we are and where we wish to go. This is not only about the IAEA but the kind of world we want to live in, in terms of development and security and the links between those two areas,' he said. Referring to a report completed early this year by an international group of eminent persons, ElBaradei stressed the fact that under present conditions the IAEA is not entirely able to cope with the dramatic changes underway around the world because its financial resources and legal authority are insufficient to fulfill the task. Former Prime Minister of Holland and Scientific Forum Chairman Ruud Lubbers then took the podium. He called for the competence, capacity and capability of the IAEA to be strengthened. 'I hope that in this Scientific Forum we reach some common denominator among the IAEA and Member States.' Former US Senator and Nuclear Threat Initiative (NTI) Co-Chairman Sam Nunn, also a keynote speaker, pointed to the issue of scarcity of resources at a time when the world seems to be heading toward a dangerous direction. 'There is a large and growing gap between the IAEA's resources and the job needed to be done... It is my hope we give the IAEA the tools it needs to protect us all,' he said. The Scientific Forum featured four sessions dedicated to nuclear energy, meeting development needs, nuclear safety and security, and IAEA safeguards and verification. From the discussions it was evident hat the Agency has over half a century of its existence assumed recognisable roles along well defined

IAEA safeguards and non-proliferation

International Nuclear Information System (INIS)

Harry, R.J.S.

1995-02-01

An overview is given of the efforts to contain the nuclear weapons proliferation during half a century of man-controlled nuclear fission. An initial policy of denial did not work, a following period of cooperation needed a gradual strengthening of international assurances on the exclusively peaceful character of the flourishing use of nuclear techniques for power generation and of other applications. The focus of the nuclear weapon proliferation concern changed from the highly developed states to developing states. The Non-Proliferation Treaty laid the basis for a unique system of voluntarily accepted international inspections to verify the peaceful use of nuclear energy. The IAEA got the task to implement this 'Full Scope Safeguards' on all nuclear material and all nuclear activities in the non-nuclear weapon states. Thanks to the structure of the IAEA, in which both proponent and states with a critical attitude take part in the decision making process on the IAEA execution of its tasks, a balanced, and widely acceptable system emerged. International developments necessitated additional improvements of the non-proliferation system. The increase of strength of sub-national groups triggered international cooperation on physical protection, about a quarter of a century ago. More recently, it appeared that NPT states with assumed nuclear weapon ambitions operated in the margins between the interpretation of IAEA safeguards and the spirit and purpose of NPT. Improvements of the IAEA safeguards and a stronger cooperation between states, including the constraints which exporting states have imposed on nuclear supplies, strengthen the safeguards system. The important reductions in the two largest nuclear weapon arsenals lead, together with the delay in the fast breeder implementation, to large stockpiles of nuclear weapon usable materials. Also in this areas new internationally credible assurances have to be obtained, that these materials will never return to nuclear

IAEA safeguards and non-proliferation

Energy Technology Data Exchange (ETDEWEB)

Harry, R J.S.

1995-02-01

An overview is given of efforts to contain the nuclear weapons proliferation during half a century of man-controlled nuclear fission. An initial policy of denial did not work, a following period of cooperation needed a gradual strengthening of international assurances on the peaceful character of the flourishing use of nuclear techniques for power generation and of other applications. The focus of the nuclear weapon proliferation concern changed from the highly developed states to developing states. The Non-Proliferation Treaty laid the basis for a unique system of voluntarily accepted international inspections to verify the peaceful use of nuclear energy. The IAEA got the task to implement this `Full Scope Safeguards` on all nuclear material and all nuclear activities in the non-nuclear weapon states. Thanks to the structure of the IAEA, in which both proponent and states with a critical attitude take part in the decision making process on the IAEA execution of its tasks, a balanced, and widely acceptable system emerged. International developments necessitated additional improvements of the non-proliferation system. The increase of strength of sub-national groups triggered international cooperation on physical protection, about a quarter of a century ago. More recently, it appeared that NPT states with assumed nuclear weapon ambitions operated in the margins between the interpretation of IAEA safeguards and the spirit and purpose of NPT. Improvements of the IAEA safeguards and a stronger cooperation between states, including the constraints which exporting states have imposed on nuclear supplies, strengthen the safeguards system. The important reductions in the two largest nuclear weapon arsenals lead, together with the delay in the fast breeder implementation, to large stockpiles of nuclear weapon usable materials. Also in this areas new internationally credible assurances have to be obtained, that these materials will never return to nuclear weapon applications.

Making a real difference: Working for the IAEA

International Nuclear Information System (INIS)

2009-01-01

The International Atomic Energy Agency (IAEA) offers challenging assignments and provides a stimulating multicultural environment for people who are interested in international work experience in a specific area of expertise. This brochure provides general information on the possibilities for employment as a Professional staff member of the IAEA and other information which may be useful to persons interested in joining the IAEA's Professional staff.

SCART guidelines. Reference report for IAEA Safety Culture Assessment Review Team (SCART)

International Nuclear Information System (INIS)

2008-01-01

The IAEA Director General stressed the role of safety culture in his concluding remarks at the Meeting of the Contracting Parties to the Convention on Nuclear Safety in 2002: 'As we have learned in other areas, it is not enough simply to have a structure; it is not enough to say that we have the necessary laws and the appropriate regulatory bodies. All these are important, but equally important is that we have in place a safety culture that gives effect to the structure that we have developed. To me, effectiveness and transparency are keys. So, it is an issue which I am pleased to see, you are giving the attention it deserves and we will continue to work with you in clarifying, developing and applying safety culture through our programmes and through our technical cooperation activities.' The concept of safety culture was initially developed by the International Nuclear Safety Advisory Group (INSAG) after the Chernobyl accident in 1986. Since then the IAEA's perspective of safety culture has expanded with time as its recognition of the complexities of the concept developed. Safety culture is considered to be specific organizational culture in all types of organizations with activities that give rise to radiation risks. The aim is to make safety culture strong and sustainable, so that safety becomes a primary focus for all activities in such organizations, even for those, which might not look safety-related at first. SCART (Safety Culture Assessment Review Team) is a safety review service, which reflects the expressed interest of Members States for methods and tools for safety culture assessment. It is a replacement for the earlier service ASCOT (Assessment of Safety Culture in Organizations Team). The IAEA Safety Fundamentals, Requirements and Guides (Safety Standards) are the basis for the SCART Safety Review Service. The reports of INSAG, identifying important current nuclear safety issues, serve also as references during a SCART mission. SCART missions are based

CINDU: Catalogue of Numerical Neutron Data Available from the IAEA Nuclear Data Unit

Energy Technology Data Exchange (ETDEWEB)

Good, W. K.; Attrae, P. M.; Ekberg, K.; Lemmel, H. D.; Lorenz, A.; Otstavnov, P. [IAEA, Nuclear Data Unit, Vienna (Austria)

1967-08-15

As a consequence of the progress in the field of international data exchange, and in compliance with the recommendations of the International Nuclear Data Committee (INDC) to the Director General of the IAEA, the Nuclear Data Unit has established a neutron data compilation center for the purpose of promoting international acquisition and exchange of basic neutron data. A specific orientation was given to this activity last year with the adoption of Operation Post-Box, according to which other major data centers submit either voluntarily or on request contributions of data to a fund held by the IAEA Nuclear Data Unit, which is in turn freely distributed to the remaining major data centers and to individuals. In the course of the last 12 months, this fund of data, embodied in the Nuclear Data Unit DASTAR file, has increased considerably as a result of the contributions by the data centers of Brookhaven, Obninsk and Saclay, as well as from collections from the IAEA Nuclear Data Unit service area. The CINDU catalog, submitted herewith, is an index of the current data holdings of the IAEA Nuclear Data Unit as of first August 1967. It serves a dual function: firstly, to act as an essential aid in the operation of the Post-Box concept, and secondly to inform data users within the IAEA Nuclear Data Unit service area of the current holdings in Vienna. A method to locate available data at any one of the data centers, including the IAEA Nuclear Data Unit, exists now in CINDA in the form of an indicator at the right hand side of the page. In addition to the external reference function filled by CINDA, the present CINDU catalog serves an internal function as the bibliographic part of DASTAR as well. This internal function required slight modifications of the CINDA format, in order to provide more comprehensive information and retrieval capabilities in the overall operation of the DASTAR system. The present form of the CINDU catalog is working satisfactorily; however

IAEA Remediation Mission Issues Final Report

International Nuclear Information System (INIS)

2011-01-01

Full text: A team of international experts today completed their assessment of the strategy and plans being considered by the Japanese authorities to remediate the areas off-site TEPCO's Fukushima Daiichi Nuclear Power Plant (NPP). Their Final Report, delivered to the Japanese authorities, is available here. ''A lot of good work, done at all levels, is on-going in Japan in the area of environmental remediation,'' said Juan Carlos Lentijo, Team Leader and General Director for Radiation Protection at Spain's nuclear regulatory authority. In the report, Japan is encouraged to continue its remediation efforts, taking into account the advice provided by the Mission. ''In the early phases of the Fukushima Daiichi accident, a very cautious approach was adopted by the Japanese authorities in terms of dealing with the handling of residue materials. It is considered right to do so,'' Lentijo said. ''However, at this point in time, we see that there is room to take a more balanced approach, focussing on the real priority areas, classifying residue materials and adopting appropriate remediation measures on the basis of the results of safety assessments for each specific situation.'' The IAEA stands ready to support Japan as it continues its efforts to remediate the environment in the area off-site the Fukushima Daiichi NPP. The IAEA sent the mission to Japan from 7 to 15 October 2011 following a request from the country's government. The mission, comprising 12 international and IAEA experts from several countries, visited numerous locations in the Fukushima Prefecture and conducted meetings in Tokyo and Fukushima with Japanese officials from several ministries and institutions. A Preliminary Summary Report was issued on 14 October. Background The accident at the Fukushima Daiichi NPP has led to elevated levels of radiation over large areas. The Government of Japan has been formulating a strategy and plans to implement countermeasures to remediate these areas. The IAEA

Guidelines for IAEA International Regulatory Review Teams (IRRTs)

International Nuclear Information System (INIS)

2002-01-01

The IAEA International Regulatory Review Team (IRRT) programme provides advice and assistance to Member States to strengthen and enhance the effectiveness of the nuclear regulatory body whilst recognizing the ultimate responsibility of each Member State for nuclear safety. The IRRT programme, initiated in 1989, is not restricted to any particular group of Member States, whether developing or industrialized, but is available to all countries with nuclear installations in operation or approaching operation. The basic concepts, purposes and functions of a national regulatory body are well recognized in all Member States having a nuclear power programme. The IAEA Safety Standards Series publication entitled 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, Safety: Requirements', No. GS-R-1 (2000), provides a general consensus reference for the practices necessary for a national organization to fulfil the regulatory purposes and discharge the regulatory functions. The Requirements also defines the terms used in these guidelines. The guidance given in the Requirements recognizes that the organizational structure and regulatory processes will vary from country to country depending on their existing constitutional, legal and administrative systems; the size and structure of their nuclear programme; the technical skills and professional and financial resources available to their regulatory body, and social customs and cultural traditions. The objective of this report is to provide guidance on the basic structure of an IRRT mission and provide a common reference both across the various areas covered by an IRRT mission and across all the missions in the programme. As such, it is addressed, principally, to the team members of IRRT missions but it also provides guidance to a host regulatory body receiving a mission. This report identifies the objectives of the IRRT mission and sets out the scope of the topic areas that are

IAEA Leads Operational Safety Mission to Muehleberg Nuclear Power Plant

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency today concluded a review of the safety practices at the Muehleberg Nuclear Power Plant (NPP) near Bern in Switzerland. The team noted a series of good practices and made recommendations and suggestions to reinforce them. The IAEA assembled the Operational Safety Review Team at the request of the Swiss government. The team, led by the IAEA's Division of Nuclear Installation Safety, performed an in-depth operational safety review from 8 to 25 October 2012. The team comprised experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Slovakia, Sweden, the United Kingdom and the United States as well as experts from the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Muehleberg NPP. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry, Emergency Planning and Preparedness, Severe Accident Management and Long-Term Operation. The OSART team made 10 recommendations and 11 suggestions related to areas where operations of Muehleberg NPP could be further improved, for example: - Plant management could improve the operating experience program and methods throughout the plant to ensure corrective actions are taken in a timely manner; - In the area of Long-Term Operation, the ageing management review for some systems and components is not complete and the environmental qualification of originally installed safety cables has not yet been revalidated for long-term operation; and - The plant provisions for the protection of persons on the site during an emergency with radioactive release can be improved to minimize health risks to plant personnel. The team also identified 10 good

IAEA and International Science and Technology Center sign cooperative agreement

International Nuclear Information System (INIS)

2008-01-01

Full text: The IAEA and the International Science and Technology Center (ISTC) today signed an agreement that calls for an increase in cooperation between the two organizations. The memorandum of understanding seeks to amplify their collaboration in the research and development of applications and technology that could contribute to the IAEA's activities in the fields of verification and nuclear security, including training and capacity building. IAEA Safeguards Director of Technical Support Nikolay Khlebnikov and ISTC Executive Director Adriaan van der Meer signed the Agreement at IAEA headquarters in Vienna on 22 October 2008. (IAEA)

IAEA Newsbriefs. V. 13, no. 2(79). Apr-May 1998

International Nuclear Information System (INIS)

1998-01-01

This issue gives brief information on the following topics: IAEA Board Meetings Set in May and June, Database of the IAEA's International Nuclear Information Systems (INIS) is being made available over the Internet free of charge, Senior Expert Group Starts Review of IAEA Programmes, IAEA Reports to Security Council on Nuclear Inspections in Iraq, Parties Consider Extending Fusion Research through the ITER Project, Status of Joint Safety and Nuclear Liability Conventions, Proposed Global Convention Against Nuclear Terrorism, Upcoming Symposia and Conferences, New IAEA Books, Nuclear Data File, and other short information

IAEA/CRP for decommissioning techniques for research reactors

Energy Technology Data Exchange (ETDEWEB)

Oh, Won Zin; Won, H. J.; Kim, K. N.; Lee, K. W.; Jung, C. H

2001-03-01

The following were studied through the project entitled 'IAEA/CRP for decommissioning techniques for research reactors 1. Decontamination technology development for TRIGA radioactive soil waste - Electrokinetic soil decontamination experimental results and its mathematical simulation 2. The 2nd IAEA/CRP for decommissioning techniques for research reactors - Meeting results and program 3. Hosting the 2001 IAEA/RCA D and D training course for research reactors and small nuclear facilities.

IAEA/CRP for decommissioning techniques for research reactors

International Nuclear Information System (INIS)

Oh, Won Zin; Won, H. J.; Kim, K. N.; Lee, K. W.; Jung, C. H.

2001-03-01

The following were studied through the project entitled 'IAEA/CRP for decommissioning techniques for research reactors 1. Decontamination technology development for TRIGA radioactive soil waste - Electrokinetic soil decontamination experimental results and its mathematical simulation 2. The 2nd IAEA/CRP for decommissioning techniques for research reactors - Meeting results and program 3. Hosting the 2001 IAEA/RCA D and D training course for research reactors and small nuclear facilities

Japanese contributions to IAEA INTOR Workshop, Phase Two A, Part 3

International Nuclear Information System (INIS)

Iida, Hiromasa; Kobayashi, Takeshi; Yamada, Masao

1988-02-01

This report corresponds to Chapter VII of Japanese contribution report to IAEA INTOR Workshop, Phase two A, Part 3. The discussions on the following tasks are reported. Task 1. Comparative study of vertical and horizontal access configuration. Task 2. Shape memory alloy. Task 3. Ferromagnetic inserts for ripple reduction. Task 4. PF coil redundancy. Task 5. Rapid replacement of divertor and first wall. Task 6. Containment of tritium and activated dust. In the above tasks, Task 2, 3 and 4 come from the Specialist Meeting on Tokamak Concept Innovation in January, 1986. (author)

IAEA activities on nuclear fuel cycle 1997

Energy Technology Data Exchange (ETDEWEB)

Oi, N [International Atomic Energy Agency, Vienna (Austria). Nuclear Fuel Cycle and Materials Section

1997-12-01

The presentation discussing the IAEA activities on nuclear fuel cycle reviews the following issues: organizational charts of IAEA, division of nuclear power and the fuel cycle, nuclear fuel cycle and materials section; 1997 budget estimates; budget trends; the nuclear fuel cycle programme.

IAEA activities on nuclear fuel cycle 1997

International Nuclear Information System (INIS)

Oi, N.

1997-01-01

The presentation discussing the IAEA activities on nuclear fuel cycle reviews the following issues: organizational charts of IAEA, division of nuclear power and the fuel cycle, nuclear fuel cycle and materials section; 1997 budget estimates; budget trends; the nuclear fuel cycle programme

IAEA inspections and Iraq's nuclear capabilities

International Nuclear Information System (INIS)

Gillen, V.A.

1992-04-01

It is reported that IAEA teams have been investigating Iraq's nuclear capabilities since May 1991 and following the Gulf War under terms of United Nations Security Council Resolution 687 directed at eliminating Iraq's weapons of mass destruction and means to produce and use them. A chronology of the events as well as the IAEA plan of further actions are described

IAEA team to visit North Korean nuclear facilities

International Nuclear Information System (INIS)

2002-01-01

A technical team from the IAEA will visit nuclear facilities in the Nyongbyon area of the Democratic People's Republic of Korea (DPRK) from 15-19 January. The visit will include the Isotope Production Laboratory, an installation that the DPRK has stated was involved in the early stages of development of their nuclear programme. Since 1993, the IAEA has been unable to fully implement its comprehensive safeguards agreement with the DPRK, and has been therefore unable to verify the completeness and correctness of the DPRK's initial 1992 declaration of its nuclear inventory. In May 2001, the IAEA proposed to the DPRK concrete steps that need to be carried out in that verification process, and indicated its readiness to start implementing these measures immediately. At a technical meeting between the DPRK and the IAEA in November 2001, the DPRK did not agree to promptly start to implement those proposals, citing the delay in implementation of the USA/DPRK Agreed Framework as the principal reason for declining. However, the DPRK did agree to a visit, not an inspection, by IAEA inspectors to the Isotope Production Laboratory. The DPRK withdrew its membership from the Agency in June 1994. The Director General encourages the DPRK to normalize its relations with the IAEA including resumption of full safeguards inspections

IAEA Director General welcomes landmark convention to combat nuclear terrorism

International Nuclear Information System (INIS)

2005-01-01

Full text: IAEA Director General Mohamed ElBaradei welcomed the adoption of an International convention against nuclear terrorism. 'This is a landmark achievement which will bolster global efforts to combat nuclear terrorism,' Dr. ElBaradei said. 'It will be a key part of international efforts to prevent terrorists from gaining access to nuclear weapons'. The United Nations General Assembly adopted the convention, The International Convention for the Suppression of Acts of Nuclear Terrorism, on 13 April 2005. The Convention strengthens the global legal framework to counter terrorist threats. Based on a proposal by the Russian Federation in 1998, the Convention focuses on criminal offences related to nuclear terrorism and covers a broad range of possible targets, including nuclear reactors as well as nuclear material and radioactive substances. Under its provisions, alleged offenders - for example any individual or group that unlawfully and intentionally possesses or uses radioactive material with the intent to cause harm - must be either extradited or prosecuted. States are also encouraged to cooperate with each other in connection with criminal investigations and extradition proceedings. The Convention further requires that any seized nuclear or radiological material be held in accordance with IAEA safeguards, and handled in keeping with the IAEA's health, safety and physical protection standards. Dr. ElBaradei also recalled that the Agency is in the process of amending the Convention on the Physical Protection of Nuclear Material, in order to broaden its scope, and in so doing, strengthen the current legal framework for securing nuclear material against illicit uses. A conference will be held from 4 to 8 July in Vienna to consider and adopt the amendments. The Convention opens for signature in September this year. Dr ElBaradei urged all States to 'sign and ratify the Convention without delay so nuclear terrorism will have no chance'. (IAEA)

IAEA Newsbriefs. V. 15, no. 3(88). Jul-Aug 2000

International Nuclear Information System (INIS)

2000-01-01

This issue gives information about the following topics: the IAEA General Conference (opening on 18 September 2000 in Vienna), IAEA's Director General welcoming of the consensus at NPT review conference, reviews of the IAEA Safeguards' implementation at the June 2000 Board of Governors, upcoming IAEA international symposia and seminars, radiation monitoring of the Irish Sea, the status of states joining international conventions in nuclear fields, survey of radiation sources in Georgia, review of the 'Nuclear World' in the IAEA Annual Report, African partnerships, the evaluation of the radiological impact of Chernobyl accident by the UNSCEAR report, and other short information

IAEA Operational Safety Team (OSART) Reviews Progress at Fessenheim Nuclear Power Plant, France

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has evaluated the French Nuclear Power Plant (NPP) at Fessenheim to assess how the facility has followed up on an Operational Safety Review Team (OSART) mission undertaken in 2009. The IAEA assembled a team of experts at the request of the Government of France to conduct the mission. Follow-up missions are standard components of the OSART programme and are conducted 18-24 months after the initial OSART mission. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the team performed its review from 7 to 11 February 2011. The team assessed how the Fessenheim NPP has addressed the recommendations and suggestions made during the 2009 OSART mission. The team was made up of experts from Slovakia, Switzerland and the IAEA. The review covered the areas of Management, Organization and Administration; Training and Qualifications; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. The conclusions of the follow-up review are based on the IAEA's Safety Standards and proven good international practices. There were 21 issues raised by the 2009 mission. During the follow-up mission, the team assessed that six issues had been resolved, thirteen had made satisfactory progress to date and two had made insufficient progress to date. 'Resolved' describes action plans for improvement that have been fully implemented; 'satisfactory progress to date' describes action plans that have been developed but are not yet fully implemented; and 'insufficient progress to date' describes situations where additional consideration or strengthening of improvement plans is necessary. Examples of issues falling into different resolution categories include: The plant has resolved the suggestion to establish a process to review initial training materials on a regular basis

IAEA Newsbriefs. V. 13, no. 4(81). Oct-Nov 1998

International Nuclear Information System (INIS)

1998-01-01

This issue gives brief information on the following topics: IAEA General Conference Concludes in Vienna, Newly Elected IAEA Board of Governors, Director General Highlights Major Work Ahead, Statement to UN General Assembly, More States Accept Strengthened Safeguards Measures, Status of Additional Protocols, Signings at IAEA General Conference, USA Backs International Nuclear Fusion Project, September Meeting on Trilateral Initiative, Results From IAEA-Supported Projects, Database of Nuclear Medicine Best Practices, 1999 Seminar on Radiopharmaceuticals in Medical Treatment, International Symposium on Marine Pollution in Monaco, Safeguards Support From France and United Kingdom, Nuclear Inspections in Iraq, States Move to Join International Safety Conventions, Safety of Radiation Sources and Security of Radioactive Materials, Technical Team Trained in IAEA-Supported Project, Scientific Forum on Water Issues, International Scientific and Technical Meetings, New IAEA Books, and other short information

IAEA Delivers Report on Nuclear Power Development to Belarus Deputy Prime Minister

International Nuclear Information System (INIS)

2012-01-01

Full text: The International Atomic Energy Agency today delivered the final report from an IAEA Integrated Nuclear Infrastructure Review (INIR) mission to Belarus. The report concludes that Belarus has made important progress in its development of nuclear infrastructure for a nuclear power programme and that Belarus is on its way to being well-prepared with its infrastructure to support the construction of a nuclear power plant. The report makes 16 recommendations and 22 specific recommendations to assist the national authorities in preparing the infrastructure necessary for the project. ''Belarus has already implemented some of the recommendations that we shared with them in June, and the Government plans to implement all the remaining ones,'' IAEA Deputy Director General Alexander Bychkov said after delivering the document to Belarusian Deputy Prime Minister Anatoly Tozik. ''This shows that the country is taking the report seriously.'' The main recommendations in the report include to revise Belarusian nuclear legislation to adequately address issues such as radioactive waste and spent fuel management, review the enforcement process, and norms relevant to civil liability for nuclear damage; to strengthen the regulatory body and the regulatory framework for licensing; and to develop comprehensive management systems for the nuclear project. Additionally, specific suggestions were made about its infrastructure development activities based on guidance contained in the publication Milestones in the Development of a National Infrastructure for Nuclear Power. ''The report acknowledges Belarus' strong expertise in radiation protection and environmental monitoring and recognizes that good coordination in the development of Belarus' nuclear power programme is beneficial,'' Bychkov said. Belarus began considering nuclear power in the 1980s and recently renewed its efforts. The Concept of Energy Security of the Republic of Belarus, promulgated in September 2007, called for

Recent advances in IAEA safeguards systems analysis

International Nuclear Information System (INIS)

Bahm, W.; Ermakov, S.; Kaniewski, J.; Lovett, J.; Pushkarjov, V.; Rosenthal, M.D.

1983-01-01

Efficient implementation of effective safeguards, the objective of the IAEA's Department of Safeguards, would be unthinkable without carrying out systematic studies on many different problems related to technical and other aspects of safeguards. The System Studies Section of the Department concentrates its efforts on such studies with the purpose of elaborating concepts, criteria, approaches and rules for the implementation of safeguards. In particular, the Section elaborates concepts and approaches for applying safeguards at the complex facilities that are expected to enter under safeguards in the future, develops approaches and rules in the areas where the Agency is still gaining experience, and assists in the implementation of safeguards whenever problems requiring non-routine solutions arise. This paper presents examples of the present activities of the System Studies Section: development of guidelines for use by facility designers in order to make safeguards easier and more effective, studies on near-real-time material accountancy, preparation of safeguards approaches for specific facility types, preparation of model inspection activity lists for different facility types and alternative safeguards approaches and preparation of safeguards policy papers containing the rules and regulations to be followed in the design and implementation of safeguards. (author)

IAEA Director General welcomes NPT consensus

International Nuclear Information System (INIS)

2000-01-01

The document informs that the Director General of the IAEA welcomed the adoption with consensus by the Review Conference of the Parties to the Treaty on the Non-Proliferation of Nuclear Weapons of the final document on the review and operation of the Treaty, and that he was pleased by the vote of confidence shown in the IAEA and its role in the implementation of the Treaty

IAEA Expert Remediation Mission to Japan Issues Preliminary Report

International Nuclear Information System (INIS)

2013-01-01

Full text: The International Atomic Energy Agency (IAEA)'s international expert mission to review remediation efforts in areas affected by the Fukushima Daiichi accident concluded today with the presentation of a Preliminary Summary Report to Japan's Senior Vice-Minister of the Environment, Shinji Inoue. The Follow-up IAEA International Mission on Remediation of Large Contaminated Areas Off-site the Fukushima Daiichi NPS recognised the huge effort and enormous resources that Japan is devoting to its remediation strategies and activities, with the aim of improving living conditions for people affected by the nuclear accident and enabling evacuees to return home. The Mission Team highlighted important progress since the first IAEA remediation mission in October 2011, noted that Japan had made good use of advice from that earlier Mission, and offered fresh advice in a number of areas where it is still possible to further improve current practices, taking into account both international standards and the experience of remediation programmes in other countries. 'Japan has done an enormous amount to reduce people's radiation exposure in the affected areas, to work towards enabling evacuees to go back to their homes and to support local communities in overcoming economic and social disruption', said team leader Juan Carlos Lentijo, Director of the Division of Fuel Cycle and Waste Technology in the IAEA Department of Nuclear Energy. 'The Mission Team has been really impressed by the involvement of a wide range of ministries, agencies and local authorities in driving these crucial remediation efforts'. Among the findings of the Mission, which was requested by the Japanese government and began on 14 October, the team welcomed the extensive provision of individual dosimeters so that residents can monitor their own radiation dose rates, helping to boost public confidence. Good progress has been made in the remediation of affected farmland, and comprehensive implementation of

Standards: An international framework for nuclear safety

International Nuclear Information System (INIS)

Versteeg, J.

2000-01-01

The IAEA, uniquely among international organizations concerned with the use of radiation, radioactive materials and nuclear energy, has statutory functions to establish safety standards and to provide for their application in Member States. The IAEA also contributes towards another major element of the 'global safety culture', namely the establishment of legally binding international agreements on safety related issues. (author)

Report on the intercomparison runs for the determination of trace and minor elements in cabbage material. IAEA-359

International Nuclear Information System (INIS)

Campbell, M.J.; Radecki, Z.; Trinkl, A.; Burns, K.I.

2000-04-01

In 1989, the IAEA decided to produce a cabbage plant reference material that could be characterised for certain agrochemical residues. The cabbage plants (Brassica oleracea var. Sabauda) were grown from seed in Seibersdorf, Austria. The plants were treated with ten different agrochemical products during their growing period. Subsequently, it was decided that the material would also be valuable as a reference material for trace element analysis and quality control purposes. The property values for the trace metal content of the cabbage material, designated IAEA 359, were to be ascribed on the basis of information received from international intercomparison exercises. In parallel, it was decided to despatch the material as part of a joint IAEA-NIST (National Institute of Standards and Technology, USA) project to certify the trace and minor element contents of a spinach reference material (NIST 1570a), in which it was to serve as a quality control material. A similar rationale was used to justify inclusion of IAEA 359 in a small scale exercise for a preliminary characterisation of another IAEA reference material, IAEA 336 Lichen. Between 1992 and 1993, the material was used in 4 projects (2 large scale and 2 smaller scale) where its trace element contents were determined. This report deals with the statistical evaluation of the pooled analytical data from these exercises

USSP-IAEA WORKSHOP ON ADVANCED SENSORS FOR SAFEGUARDS

International Nuclear Information System (INIS)

PEPPER, S.; QUEIROLO, A.; ZENDEL, M.; WHICHELLO, J.; ANNESE, C.; GRIEBE, J.; GRIEBE, R.

2007-01-01

The IAEA Medium Term Strategy (2006-2011) defines a number of specific goals in respect to the IAEA's ability to provide assurances to the international community regarding the peaceful use of nuclear energy through States adherences to their respective non-proliferation treaty commitments. The IAEA has long used and still needs the best possible sensors to detect and measure nuclear material. The Department of Safeguards, recognizing the importance of safeguards-oriented R and D, especially targeting improved detection capabilities for undeclared facilities, materials and activities, initiated a number of activities in early 2005. The initiatives included letters to Member State Support Programs (MSSPs), personal contacts with known technology holders, topical meetings, consultant reviews of safeguards technology, and special workshops to identify new and novel technologies and methodologies. In support of this objective, the United States Support Program to IAEA Safeguards hosted a workshop on ''Advanced Sensors for Safeguards'' in Santa Fe, New Mexico, from April 23-27, 2007. The Organizational Analysis Corporation, a U.S.-based management consulting firm, organized and facilitated the workshop. The workshop's goal was to help the IAEA identify and plan for new sensors for safeguards implementation. The workshop, which was attended by representatives of seven member states and international organizations, included presentations by technology holders and developers on new technologies thought to have relevance to international safeguards, but not yet in use by the IAEA. The presentations were followed by facilitated breakout sessions where the participants considered two scenarios typical of what IAEA inspectors might face in the field. One scenario focused on an enrichment plant; the other scenario focused on a research reactor. The participants brainstormed using the technologies presented by the participants and other technologies known to them to propose

Excerpts from the introductory statement to the IAEA Board of Governors, Vienna, 7 December 2000

International Nuclear Information System (INIS)

ElBaradei, M.

2000-01-01

The document contains excerpts from the Introductory Statement made by the Director General of the IAEA at the IAEA Board of Governors on 7 December 2000. The following aspects from the Agency's activities are briefly presented: nuclear verification (status of integrated safeguards, plan of action for safeguards agreements and additional protocols, safeguards related to the Democratic People's Republic of Korea), technology issues (results of the 6th Conference of the Parties to the Convention on Climate Change, international project on innovative reactor and fuel cycle technologies), and safety issues (depleted uranium, safety standard discussions with the International Civil Aviation Organization, exchange of regulators or other safety personnel, emergency response co-ordination)

Outcomes of the IAEA programme on the radiological protection of the environment

International Nuclear Information System (INIS)

Robinson, C.

2002-01-01

Since the late 1990's the work of the International Atomic Energy Agency (IAEA), relating to the effects of radiation on species other than man, has been focused on defining and clarifying issues related to the development of an international framework to address the protection of the environment, or living elements within it, from the effects of ionising radiation. In 1999, IAEA-TECDOC-1091, entitled Protection of the Environment from the Effects of Ionising Radiation: A Report for Discussion, was published. This report explored the various issues and approaches that would need to be resolved in order to establish an environmental protection framework and associated criteria. Relevant principles, policies and regulatory approaches were reviewed and the factors that may affect future developments of a protection system were identified. The report concluded that, although improved information was required in several areas, there was sufficient knowledge of the effects of ionising radiation on organisms to move forward. Following publication of this report, IAEA activities have continued on: a) the elaboration of the ethics and principles underlying environmental protection, paying particular attention to their implications for the development of an approach for radiological protection of the environment; and, h) fostering information exchange by holding a series of Specialists Meetings on environmental radiation protection, the most recent of which took place in November 2001. The long-term aim of this work is to establish consensual IAEA Safety Standards on environmental radiation protection, in collaboration with other relevant international organisations. This paper will provide a summary of IAEA work to date on the development of a framework for protection of the environment from ionising radiation, paying particular attention to the recently published IAEA-TECDOC-1270 on Ethical Considerations in protecting the Environment front the Effects of Ionising

Finnish support programme to IAEA safeguards. Annual report 1994; Suomen tukiohjelma IAEA:n safeguards-valvonnalle. Vuoden 1994 toimintakertomus

Energy Technology Data Exchange (ETDEWEB)

Tarvainen, M [ed.

1995-05-01

Implementation of the Finnish Support Programme to IAEA Safeguards (FINSP) during the calender year in question is summarized. FINSP is carried out trough separate tasks concentrating on verification of nuclear material, training and expert services to the IAEA. In addition to the Finnish summary, the report includes detailed description of each task in English.

Business transactions and standards. Towards a system of concepts and a method for early problem identification in standard implementation projects

NARCIS (Netherlands)

Rukanova, B.D.

2005-01-01

To summarize, with respect to research question one we constructed a system of concepts, while in answer to research question two we proposed a method of how to apply this system of concepts in practice in order to identify potential problems in early stages of standard implementation projects.

IAEA coordinated research project on thermal-hydraulics of Supercritical Water-Cooled Reactors (SCWRs)

International Nuclear Information System (INIS)

Yamada, K.; Aksan, S. N.

2012-01-01

The Supercritical Water-Cooled Reactor (SCWR) is an innovative water-cooled reactor concept, which uses supercritical pressure water as reactor coolant. It has been attracting interest of many researchers in various countries mainly due to its benefits of high thermal efficiency and simple primary systems, resulting in low capital cost. The IAEA started in 2008 a Coordinated Research Project (CRP) on Thermal-Hydraulics of SCWRs as a forum to foster the exchange of technical information and international collaboration in research and development. This paper summarizes the activities and current status of the CRP, as well as major progress achieved to date. At present, 15 institutions closely collaborate in several tasks. Some organizations have been conducting thermal-hydraulics experiments and analysing the data, and others have been participating in code-to-test and/or code-to-code benchmark exercises. The expected outputs of the CRP are also discussed. Finally, the paper introduces several IAEA activities relating to or arising from the CRP. (authors)

Problems encountered in embodying the principles of ICRP-26 and the revised IAEA safety standards into UK national legislation

International Nuclear Information System (INIS)

Beaver, P.F.

1979-01-01

This paper describes the United Kingdom procedures and format for safety legislation and goes on to show how the necessary legislation for radiological protection will fit into the general framework. The United Kingdom, as a member of the European Community and EURATOM, is bound to implement the Euratom Directive on radiological protection within the next few years. The latest draft of the Directive takes account of the recommendations of ICRP-26 and further, a recent draft of the revised IAEA Basic Safety Standards is a composite of both the Directive and ICRP-26. Thus, the effect of embodying the principles of the Directive is to embody the principles of ICRP-26 and the Basic Safety Standards. Some of the problems which have been met are described and in particular there is discussion of the problems arising from the incorporation of the three ICRP-26 facets of dose control, namely justification, optimization and limitation, into a legislative package. The UK system of evolving safety legislation now requires considerable participation by all the parties affected (or by their representatives). This paper indicates that the involvement of persons affected, coupled with a legislative package which consists of a hierarchy of (a) regulations; (b) codes of practice; and (c) guidance notes, will result in the fundamental principles of ICRP-26 being incorporated into UK legislation in a totally acceptable way. (author)

Japanese authorities inform IAEA about accident at nuclear plant

International Nuclear Information System (INIS)

2004-01-01

Full text: The IAEA today received information from Japanese nuclear regulatory authorities about an accident in the steam generator turbine circuit of the Mihama Nuclear Power Plant (unit 3). According to the Japanese nuclear authorities this is a non-radioactive part of the plant. The regulatory body has reported that four contract employees died and 7 were injured, and stated that there was no release of radioactivity. The IAEA continues to be in contact with Japanese authorities and expects to receive updates on a continuous basis. No request for IAEA assistance has been received at this time. (IAEA)

IAEA Newsbriefs. V. 13, no. 3(80). Jul-Aug 1998

International Nuclear Information System (INIS)

1998-01-01

This issue gives brief information on the following topics: IAEA General Conference Opens 21 September in Vienna, IAEA Board Concludes Mid-Year Review: Approves Six More Protocols to Safeguards Agreements, Safeguards Implementation in 1997 Reported, Study of Radiological Situation at Mururoa and Fangataufa Atolls, Nuclear Inspections in Iraq Seeking Further Clarification, Pioneering Waste Repository Gets 'Green Light' in the USA, Status of International Conventions, Nuclear Techniques Targeted for Studying Water Pollution, Zimbabwe Farmers Realize Benefits from Nuclear Techniques, Waging a War Against Insect Pests, IAEA and WCO Formally Join Forces Against Illicit Trafficking, Annual Report for 1997, Range of Topics on IAEA Meeting Agenda, New IAEA Books, and other short information

IAEA Newsbriefs. V. 10, no. 2(68). Jun-Jul 1995

International Nuclear Information System (INIS)

1995-01-01

This issue gives brief information on the following topics: IAEA General Conference opens in September in Vienna, IAEA Board of Governors' June meetings (Safeguards proposals, Technical cooperation, Radiation safety, Radioactive waste management, Liability for nuclear damage, IAEA regular budget for 1996), NPT Conference reaffirms support for IAEA roles, Director General addresses NPT Conference, Seminar on nuclear waste management in Russian Federation, Safety Reviews of Medzamor in Armenia, Update on Nuclear Safety Convention, Cuba and Brazil: Public information seminars, India: Donation to the IAEA Laboratories, Simulated emergency tests global procedures, INIS: Happy Anniversary, China hosts international isotope conference, Nuclear power: Status and outlook, and other short information

Safety experts complete second IAEA regulatory review of UK nuclear regulator

International Nuclear Information System (INIS)

2009-01-01

Full text: Nuclear safety experts today concluded a 10-day mission to peer-review the UK Nuclear Regulator: Health and Safety Executive (HSE), Nuclear Directorate (ND). At the request of the UK Government, the International Atomic Energy Agency assembled a team of ten high-level regulatory experts from eight nations to conduct the Integrated Regulatory Review Service (IRRS) mission. The mission was the second of three planned IRRS missions for the United Kingdom. The first was held in March 2006 to begin a process to assess the nation's readiness to regulate and license new reactor designs, considered as a result of the Energy Policy review initiated by the British Prime Minister and the Secretary of State for Trade and Industry (DTI) in 2005. The IRRS team leader Mr. William Borchardt, Executive Director of Operations from the US Nuclear Regulatory Commission, stated, ''The IAEA IRRS serves an important role in both benchmarking against its safety standards and in promoting dialogue between nuclear safety regulators from around the world.'' During the 2nd mission the IRRS the team reviewed HSE/ND progress since the first IRRS mission and recent regulatory developments, the regulation of operating power plants and fuel cycle facilities, the inspection and enforcement programme for nuclear power plants and fuel cycle facilities, and the emergency preparedness and response programme. The IAEA found that HSE/ND has made significant progress toward improving its effectiveness in regulating existing nuclear power plants and in preparing to license new nuclear reactors designs. Many of the findings identified in the 2006 report had been fully addressed and therefore could be considered closed, the others are being addressed in accordance with a comprehensive action plan. IRRS team members visited the Heysham 1 Nuclear Power Plant near Lancaster, the Sellafield site at Cumbria and the Strategic Control Centre at Hutton, and they met senior managers from HSE and a UK

Analysis of normative requirements for the development and implementation of a quality management system in Brazilian nuclear installations and activities

International Nuclear Information System (INIS)

Kibrit, Eduardo

2008-01-01

The present work identifies, characterizes and analyses the normative requirements for the development and implementation of quality management systems in Brazilian nuclear installations and activities. The requirements established in standards IAEA GS-R-3, IAEA GS-G-3.1, IAEA DS 349, NBR ISO 9001:2000 e CNEN-NN-1.16 are critically analyzed. A correlation matrix of the applicable standards is presented and the related topics among them are identified. The standards IAEA GS-R-3, IAEA GS-G-3.1 and IAEA DS 349 define general requirements for establishing, implementing, assessing and continually improving an integrated management system in nuclear installations and activities, in IAEA member countries. The standard NBR ISO 9001:2000 establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard CNEN NN-1.16 establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The standard IAEA GS-R-3 that replaces the code IAEA 50-C-Q introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concepts of 'Quality Assurance' and 'Quality Management'. This new approach is aligned with the current tendency incorporating requirements of quality, safety, health, environment, security, economics and other in a unique management system. Examples of quality management systems implemented by Brazilian nuclear organizations and by nuclear organizations outside Brazil are analyzed and considered in the discussion of results. (author)

Analysis of normative requirements for the development and implementation of a quality management system in Brazilian nuclear installations and activities; Analise de requisitos normativos para o desenvolvimento e a implementacao de um sistema de gestao da qualidade em instalacoes e atividades nucleares brasileiras

Energy Technology Data Exchange (ETDEWEB)

Kibrit, Eduardo

2008-07-01

The present work identifies, characterizes and analyses the normative requirements for the development and implementation of quality management systems in Brazilian nuclear installations and activities. The requirements established in standards IAEA GS-R-3, IAEA GS-G-3.1, IAEA DS 349, NBR ISO 9001:2000 e CNEN-NN-1.16 are critically analyzed. A correlation matrix of the applicable standards is presented and the related topics among them are identified. The standards IAEA GS-R-3, IAEA GS-G-3.1 and IAEA DS 349 define general requirements for establishing, implementing, assessing and continually improving an integrated management system in nuclear installations and activities, in IAEA member countries. The standard NBR ISO 9001:2000 establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard CNEN NN-1.16 establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The standard IAEA GS-R-3 that replaces the code IAEA 50-C-Q introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concepts of 'Quality Assurance' and 'Quality Management'. This new approach is aligned with the current tendency incorporating requirements of quality, safety, health, environment, security, economics and other in a unique management system. Examples of quality management systems implemented by Brazilian nuclear organizations and by nuclear organizations outside Brazil are analyzed and considered in the discussion of results. (author)

Analysis of normative requirements for the development and implementation of a quality management system in Brazilian nuclear installations and activities; Analise de requisitos normativos para o desenvolvimento e a implementacao de um sistema de gestao da qualidade em instalacoes e atividades nucleares brasileiras

Energy Technology Data Exchange (ETDEWEB)

Kibrit, Eduardo

2008-07-01

The present work identifies, characterizes and analyses the normative requirements for the development and implementation of quality management systems in Brazilian nuclear installations and activities. The requirements established in standards IAEA GS-R-3, IAEA GS-G-3.1, IAEA DS 349, NBR ISO 9001:2000 e CNEN-NN-1.16 are critically analyzed. A correlation matrix of the applicable standards is presented and the related topics among them are identified. The standards IAEA GS-R-3, IAEA GS-G-3.1 and IAEA DS 349 define general requirements for establishing, implementing, assessing and continually improving an integrated management system in nuclear installations and activities, in IAEA member countries. The standard NBR ISO 9001:2000 establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard CNEN NN-1.16 establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The standard IAEA GS-R-3 that replaces the code IAEA 50-C-Q introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concepts of 'Quality Assurance' and 'Quality Management'. This new approach is aligned with the current tendency incorporating requirements of quality, safety, health, environment, security, economics and other in a unique management system. Examples of quality management systems implemented by Brazilian nuclear organizations and by nuclear organizations outside Brazil are analyzed and considered in the discussion of results. (author)

Newly elected IAEA Board of Governors

International Nuclear Information System (INIS)

2000-01-01

The document gives information about the election of 11 Member States to the IAEA Board of Governors, the 35-member policy-making body, during the 44th regular session of the IAEA's General Conference (18 - 22 September 2000, Austria Center, Vienna). The newly elected Member States are: Argentina, Egypt, Ghana, Ireland, Libyan Arab Jamahiriya, Mexico, Pakistan, Peru, Switzerland, Thailand, Ukraine. The other 24 Member States of the Board are also given

Newsbriefs www.iaea.org. January 2002

International Nuclear Information System (INIS)

2002-01-01

In this newsbrief the topics covered include: categories of risk, nuclear materials, nuclear facilities, and radioactive sources; a special session of IAEA experts meeting on the subject; financing the prevention of terrorism; nuclear security discussed by the IAEA Board of Governors; technical cooperation for security; use of electron beam scanning for mail safety; sustainable development; radioactive waste management; health programs in Latin America; landmine cleanup; clean water programmes

IAEA '77: between politics and factual constraints

International Nuclear Information System (INIS)

Freytag, A.

1976-01-01

The IAEA's organization of its 20th General Conference at Rio de Janeiro clearly underlined the importance of a comprehensive international transfer of nuclear technology. Despite all efforts to keep the Agency out of general political confrontations, the Conference was tinged politically by the PLO and South Africa problems. Besides the next five year program, which was agreed upon in the light of existing factual constraints, the support and control functions of the IAEA and next year's Salzburg Fuel Cycle Conference were other main topics of discussion. The 1977 IAEA budget was approved at a level of 43.5 million, the General Fund at 6.5 million. (orig.) [de

Lessons learned from IAEA fire safety missions

International Nuclear Information System (INIS)

Lee, S.P.

1998-01-01

The IAEA has conducted expert missions to evaluate fire safety at the following nuclear power plants: the Zaporozhe plant in the Ukraine, the Borselle plant in the Netherlands, the Medzamor plant in Armenia, the Karachi plant in Pakistan, the Temelin plant in the Czech Republic, and the Laguna Verde plant in Mexico. The scope of these missions varied in subject and depth. The teams sent from the IAEA consisted of external fire experts and IAEA staff. All the missions were of great use to the host countries. The participating experts also benefited significantly. A summary of the missions and their findings is given. (author)

IAEA Team Reviews Safety Progress at French Nuclear Power Plant 19-23 May 2014

International Nuclear Information System (INIS)

2014-01-01

An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has evaluated the Gravelines Nuclear Power Plant (NPP) in France to assess how the station has followed up on an Operational Safety Review Team (OSART) mission undertaken in 2012. The IAEA assembled a team of experts at the request of the Government of France to conduct the follow-up OSART mission at Gravelines NPP from 19 to 23 May 2014. Follow-up missions are standard components of the OSART programme; they are typically conducted 15-24 months after the initial OSART mission. The IAEA mission in 2012 made a number of recommendations and suggestions for consideration by the Gravelines NPP operators. The station thoroughly analyzed the OSART recommendations and suggestions and developed corrective action plans. In 18 months, the Gravelines plant has achieved the level ''resolved;; or ''satisfactory progress'' in almost all of the recommendations and suggestions made by the OSART in November 2012. During the follow-up mission, the team assessed that the operators have resolved the issues in several areas, including: Undertaking initiatives to improve fire prevention; Reinforcing contamination control practices; and Enhancing capabilities to protect emergency workers in the event of a release of radioactivity. The team identified some issues which have achieved satisfactory progress toward resolution, but need further work, including: Further improvement of measures to preventing the ingress of items or chemicals into circuits and equipment; Comprehensive application of the corrective actions programme; and Reinforcement of the containment protection system in the event of an extremely adverse situation. The team identified the following issue as one which has made insufficient progress toward resolution and needs further work: Emergency response arrangements do not follow current IAEA safety standards recommending that the plant should have a person on

Nuclear station safety standardization from a risk concept

International Nuclear Information System (INIS)

Veksler, L.M.

1986-01-01

This paper presents a method of standardizing safety-system reliability on an entirely new basis: all hypothetical accidents are approximated as groups, for each of which one proposes permissible frequencies on the basis of the risk concept. In this risk concept, the ''average person'' is a person living near a nuclear station or working in it, who is of average age, average state of health, and so on. Therefore, the risk can be found by summing the estimated individual risks for a particular group in the population followed by division by the number of people in that group. Basic assumptions in deriving permissible safety-system reliability are presented. Estimated permissible failure probabilities are given to illustrate the proposed method and to refine the initial data. The probabilities may also be used to lay down the reliability requirements for safety systems in particular nuclear stations on the risk basis

Safety of evolutionary and innovative nuclear reactors: IAEA activities and world efforts

International Nuclear Information System (INIS)

Saito, T.; Gasparini, M.

2004-01-01

'Defence in Depth' approach constitutes the basis of the IAEA safety standards for nuclear power plants. Lessons learned from the current generation of reactors suggest that, for the next generation of reactor designs, the Defence in Depth philosophy should be retained, and that its implementation should be guided by the probabilistic insights. Recent developments in the area of general safety requirements based on Defence in Depth approach are examined and summarized. Global efforts to harmonize safety requirements for evolutionary nuclear power plants have involved many countries and organizations such as IAEA, US EPRI and European Utility EUR Organization. In recent years, developments of innovative nuclear power plants are also being discussed. The IAEA is currently developing a safety approach specifically for innovative nuclear reactors. This approach will eventually lead to a proposal of safety requirements for innovative reactors. Such activities related to safety requirements of evolutionary and innovative reactors are introduced. Various evolutionary and innovative reactor designs are reported in the world. The safety design features of evolutionary large LWRs, innovative LWRs, Modular High Temperature Gas Reactors and Small Liquid Metal Cooled LMRs are also introduced. Enhanced safety features proposed in such reactors are discussed and summarized according to the levels of Defence in Depth. For future nuclear plants, international cooperation and harmonization, especially in the area of safety, appear to be inevitable. Based on the past experience with many member states, the IAEA believes itself to be the uniquely positioned international organization to play this key role. (authors)

A multilingual gold-standard corpus for biomedical concept recognition: the Mantra GSC.

Science.gov (United States)

Kors, Jan A; Clematide, Simon; Akhondi, Saber A; van Mulligen, Erik M; Rebholz-Schuhmann, Dietrich

2015-09-01

To create a multilingual gold-standard corpus for biomedical concept recognition. We selected text units from different parallel corpora (Medline abstract titles, drug labels, biomedical patent claims) in English, French, German, Spanish, and Dutch. Three annotators per language independently annotated the biomedical concepts, based on a subset of the Unified Medical Language System and covering a wide range of semantic groups. To reduce the annotation workload, automatically generated preannotations were provided. Individual annotations were automatically harmonized and then adjudicated, and cross-language consistency checks were carried out to arrive at the final annotations. The number of final annotations was 5530. Inter-annotator agreement scores indicate good agreement (median F-score 0.79), and are similar to those between individual annotators and the gold standard. The automatically generated harmonized annotation set for each language performed equally well as the best annotator for that language. The use of automatic preannotations, harmonized annotations, and parallel corpora helped to keep the manual annotation efforts manageable. The inter-annotator agreement scores provide a reference standard for gauging the performance of automatic annotation techniques. To our knowledge, this is the first gold-standard corpus for biomedical concept recognition in languages other than English. Other distinguishing features are the wide variety of semantic groups that are being covered, and the diversity of text genres that were annotated. © The Author 2015. Published by Oxford University Press on behalf of the American Medical Informatics Association.

Future direction for implementing the multilateral cooperation with the IAEA

Energy Technology Data Exchange (ETDEWEB)

Kim, Kyoung Pyo; Hong, Young Don

1999-03-01

Korea has achieved remarkable results in the development of nuclear technology over the past years. Nuclear R and D programs have been actively pursued with the aim of enhancing nuclear technological capability to the level of nuclear advanced countries by early 2000. Worth noting is the fact that the IAEA has played an important role in facilitating Korea's acquisition of advanced nuclear technologies by participating in IAEA technical cooperation programmes, and technical cooperation with the IAEA has laid a firm groundwork for Korea to achieve self-reliance in nuclear technology. Technical cooperation with the IAEA should be steadily pursued so that Korea can play a leading role in the international nuclear arena in the years to come. Up to now, the study of major programmes and of the current status of overall technical cooperation projects, which have been implemented by the IAEA, has been insufficient. It should be noted that analysis of the assistance provided by the IAEA leaves something to be desired. In this regard, analyzing the current status of technical cooperation projects as well as recommending policy direction is required in a bid to implement IAEA technical cooperation projects systematically. Korea's status within the IAEA, including activities in the Advisory Committee and the current status of its participation in Coordinated Research Programmes (CRP) and other major programmes underway, is presented in this report. The policy direction for and implementation status of IAEA technical cooperation programmes are explained at length. The current status of technical cooperation programmes carried out in the 1997-1998 cycle and those to be implemented in the 1992-2000 cycle are also described in this report. Strategies for upgrading Korea's status within the IAEA as well as directions for nuclear cooperation through the IAEA were presented in this study to positively deal with rapid changes in the international nuclear arena and to

Future direction for implementing the multilateral cooperation with the IAEA

International Nuclear Information System (INIS)

Kim, Kyoung Pyo; Hong, Young Don

1999-03-01

Korea has achieved remarkable results in the development of nuclear technology over the past years. Nuclear R and D programs have been actively pursued with the aim of enhancing nuclear technological capability to the level of nuclear advanced countries by early 2000. Worth noting is the fact that the IAEA has played an important role in facilitating Korea's acquisition of advanced nuclear technologies by participating in IAEA technical cooperation programmes, and technical cooperation with the IAEA has laid a firm groundwork for Korea to achieve self-reliance in nuclear technology. Technical cooperation with the IAEA should be steadily pursued so that Korea can play a leading role in the international nuclear arena in the years to come. Up to now, the study of major programmes and of the current status of overall technical cooperation projects, which have been implemented by the IAEA, has been insufficient. It should be noted that analysis of the assistance provided by the IAEA leaves something to be desired. In this regard, analyzing the current status of technical cooperation projects as well as recommending policy direction is required in a bid to implement IAEA technical cooperation projects systematically. Korea's status within the IAEA, including activities in the Advisory Committee and the current status of its participation in Coordinated Research Programmes (CRP) and other major programmes underway, is presented in this report. The policy direction for and implementation status of IAEA technical cooperation programmes are explained at length. The current status of technical cooperation programmes carried out in the 1997-1998 cycle and those to be implemented in the 1992-2000 cycle are also described in this report. Strategies for upgrading Korea's status within the IAEA as well as directions for nuclear cooperation through the IAEA were presented in this study to positively deal with rapid changes in the international nuclear arena and to efficiently

Standard setting in medical education: fundamental concepts and emerging challenges.

Science.gov (United States)

Mortaz Hejri, Sara; Jalili, Mohammad

2014-01-01

The process of determining the minimum pass level to separate the competent students from those who do not perform well enough is called standard setting. A large number of methods are widely used to set cut-scores for both written and clinical examinations. There are some challenging issues pertaining to any standard setting procedure. Ignoring these concerns would result in a large dispute regarding the credibility and defensibility of the method. The goal of this review is to provide a basic understanding of the key concepts and challenges in standard setting and to suggest some recommendations to overcome the challenging issues for educators and policymakers who are dealing with decision-making in this field.

Nuclear power information at the IAEA

International Nuclear Information System (INIS)

Spiegelberg-Planer, R.

1999-01-01

The reliable and adequate supply of energy, and especially electricity, is necessary not only for economic development but, for economic and political stability. Since its establishment in the second half of the 20th century, nuclear power has evolved from the research and development stage to a mature industry that supplies more than 17% of the world's total electricity. Well designed, constructed and operated nuclear power plants have proved to be reliable, safe and economic. Although many countries are heavily reliant on nuclear power, in the last decade, expansion of nuclear power has been almost stagnating in the Western industrialized world, experiencing a low growth in Eastern Europe and expanding only in East Asia. On one side, one of the most important aims of the IAEA is to support the national effort to improve the nuclear power generation and to assist in promoting improvements in their safe, reliable and economic performance. On the other side, the IAEA also provides the only truly international forum for exchange, collection and dissemination of information in many areas related to nuclear energy. The Power Reactor Information System, PRIS, is one fundamental tool for these activities. The PRIS database is managed by the staff of the Nuclear Power Division in the IAEA. In the scope of PRIS various publications and reports have been published, as well as the IAEA has been satisfying request from Member States ranging from simple query to complex analysis. This paper presents an overview of the status of nuclear power world-wide and the related IAEA activities on collecting and disseminating nuclear power information. (author)

Nuclear power information at the IAEA

International Nuclear Information System (INIS)

Spiegelberg-Planer, R.

2001-01-01

The reliable and adequate supply of energy, and especially electricity, is necessary not only for economic development but, for economic and political stability. Since its establishment in the in the second half of the 20th century, nuclear power has evolved from the research and development stage to a mature industry that supplies more than 17% of the world's total electricity. Well designed, constructed and operated nuclear power plants have proved to be reliable, safe and economic. Although many countries are heavily reliant on nuclear power, in the last decade, expansion of nuclear power has been almost stagnating in the Western industrialized world, experiencing a low growth in Eastern Europe and expanding only in East Asia. On one side, one of the most important aims of the IAEA is to support the national effort to improve the nuclear power generation and to assist in promoting improvements in their safe, reliable and economic performance. On the other side, the IAEA also provides the only truly international forum for exchange, collection and dissemination of information in many areas related to nuclear energy. The Power Reactor Information System, PRIS, is one fundamental tool for these activities. The PRIS database is managed by the staff of the Nuclear Power Division in the IAEA. In the scope of PRIS various publications and reports have been published, as well as the IAEA has been satisfying request from Member States ranging from simple query to complex analysis. This paper presents an overview of the status of nuclear power world-wide and the related IAEA activities on collecting and disseminating nuclear power information. (author)

Contribution of the Member State Support Programmes to IAEA safeguards

International Nuclear Information System (INIS)

Fortakov, V.; Gardiner, D.; Rautjaervi, J.

1999-01-01

Over the last twenty years, Member States of the International Atomic Energy Agency (IAEA) have provided invaluable technical support to IAEA Safeguards. This support has covered practically all aspects of traditional safeguards activities and also those activities recently proposed and introduced for strengthening the safeguards system. As of August 1997, there were fourteen Member States, plus EURATOM, with active programmes in support of IAEA safeguards and the activities conducted under these Member State Support Programmes (MSSPs) are currently valued at an annual twenty million dollars of extra-budgetary contribution to the IAEA. The overall administration in the IAEA of the support programmes is the responsibility of Support Programmes Administration (SPA) in the Safeguards Division of Technical Services. This paper describes the roles and the contributions of the MSSPs, the functions of the MSSP administration activities, and the vital importance the IAEA attaches to the MSSPs. (author)

New IAEA guidance on safety culture

International Nuclear Information System (INIS)

Haage, Monica; )

2012-01-01

Monica Haage described a project for Kozloduy Nuclear Power Plant in Bulgaria which was also funded by the Norwegian government. This project included the development of guidance documents and training on self-assessment and continuous improvement of safety culture. A draft IAEA safety culture survey was also developed as part of this project in collaboration with St Mary's University, Canada. This project was conducted in parallel with an IAEA project to develop new safety reports on safety culture self-assessment and continuous improvement. A safety report on safety culture during the pre-operational phases of NPPs has also been drafted. The IAEA approach to safety culture assessment was outlined and core principles of the approach were discussed. These include the use of several assessment methods (survey, interview, observation, focus groups, document review), and two distinct levels of analysis. The first is a descriptive analysis of the observed cultural characteristics from each assessment method and overarching themes. This is followed by a 'normative' analysis comparing what has been observed with the desirable characteristics of a strong, positive, safety culture, as defined by the IAEA safety culture framework. The application of this approach during recent Operational Safety Assessment Review Team (OSART) missions was described along with key learning points

ISSAS guidelines. Reference report for IAEA SSAC advisory service

International Nuclear Information System (INIS)

2005-01-01

All comprehensive safeguards agreements between the IAEA and Member States concluded on the basis of INFCIRC/153 (Corrected) require the Member State to establish and maintain a system of accounting for and control of nuclear material subject to safeguards. In the years following the negotiation of INFCIRC/153, the IAEA's Secretariat and a large group of experts from Member States collaborated in the production of a set of guidelines to assist Member States in establishing their State system of accounting for and control of nuclear materials (SSAC). These guidelines, termed 'Guidelines for States' Systems of Accounting for and Control of Nuclear Materials', were published in 1980 as part of the IAEA's information series on the then developing safeguards system (IAEA/SG/INF/2). However, events over the past decade have changed the circumstances and requirements of the safeguards system. The IAEA, with support and assistance from Member States, embarked on an extensive multiyear effort to strengthen the safeguards system by increasing the IAEA's capability to detect undeclared nuclear material and activities. The centre-piece of this effort is the Model Protocol Additional to Safeguards Agreements (referred to as the 'additional protocol' and contained in INFCIRC/540 (Corrected)) approved by the Board of Governors in May 1997. The central components of strengthened safeguards and the additional protocol are increased access to information and increased physical access. The effective and efficient implementation of the strengthened safeguards system requires the SSACs to be effective and to cooperate closely with the IAEA. To achieve this aim the IAEA is, inter alia, revising IAEA/SG/INF/2, providing training and equipment to SSAC Authorities and providing an advisory service to Member States known as the IAEA SSAC Advisory Service (ISSAS). Accounting for and control of nuclear material is also key for nuclear security. General Conference resolutions (e.g. GC(48)/RES

Excerpts from the introductory statement by IAEA Director General. IAEA Board of Governors, Vienna, 8 December 1997

International Nuclear Information System (INIS)

ElBaradei, M.

1997-01-01

The document contains excerpts from the Introductory Statement made by the Director General of the IAEA at the IAEA Board of Governors on 8 December 1997. The following aspects from the Agency's activity are presented: nuclear energy, Agency's inspections in Iraq in relation to its clandestine nuclear programme, Agency's involvement in safeguards verification in the Democratic People's Republic of Korea (DPRK), and conclusion of safeguards agreements and additional protocols

IAEA Expert Team Returns from Iran

International Nuclear Information System (INIS)

2012-01-01

Full text: A senior IAEA expert team is returning from Iran after two days of discussions with Iranian officials held on 20 and 21 February 2012. The meeting followed previous discussions held on 29 to 31 January 2012. During both the first and second round of discussions, the Agency team requested access to the military site at Parchin. Iran did not grant permission for this visit to take place. Intensive efforts were made to reach agreement on a document facilitating the clarification of unresolved issues in connection with Iran's nuclear programme, particularly those relating to possible military dimensions. Unfortunately, agreement was not reached on this document. 'It is disappointing that Iran did not accept our request to visit Parchin during the first or second meetings', IAEA Director General Yukiya Amano said. 'We engaged in a constructive spirit, but no agreement was reached'. (IAEA)

Establishing a Nuclear Power Programme: IAEA Recommended approach

International Nuclear Information System (INIS)

Van Sickle, Matthew

2013-01-01

IAEA Recommended approach: All newcomers are working closely with the IAEA, using IAEA guidance and hosting international peer review missions. Newcomers’ Top Issues: • How do I start? • Is there public support? • Do I have the people? • Can I find the money? • What am I going to do with the waste? • Is it safe? Can I manage if there is an accident? A pre-feasibility study should provide high level answers to all these questions and allow a knowledgeable decision

The international ISOE programme. ISOE IAEA technical centre activities

International Nuclear Information System (INIS)

Gustafsson, M.

1996-01-01

The objective of the sub-programme on Occupational Radiation Protection in the International Atomic Energy Agency, IAEA, is to promote a harmonized approach to optimizing occupational radiation protection by developing guidelines for controlling radiation doses in the workplace and on current occupational radiation protection techniques. A significant part of this programme is the provision of assistance to developing member states to bring their radiation safety infrastructure to an appropriate level for the usage of radiation in the state. In consistence with these objectives the IAEA has been involved with the ISOE programme from its inception and has contributed actively to its growth. In 1993 an arrangement was agreed between the IAEA and the Nuclear Energy Agency, NEA, by which the IAEA co-sponsors ISOE inviting those IAEA member states which are not members of the NEA to participate cost-free in the programme. (author)

IAEA Monitors Marine Radioactivity

International Nuclear Information System (INIS)

Dixit, Aabha; Kaiser, Peter

2013-01-01

The IAEA assists Member States in using scientific tools to precisely identify and track nuclear and nonnuclear contaminants, as well as to investigate their biological effects on the marine ecosystem

Newly elected IAEA Board of Governors

International Nuclear Information System (INIS)

2001-01-01

The document gives information about the election of 11 Member States to the IAEA Board of Governors, the 35-member policy-making body, during the 45th regular session of the IAEA's General Conference (17-21 September 2001, Austria Center, Vienna). The newly elected Member States are: Bulgaria, Burkina Faso, Chile, Colombia, Islamic Republic of Iran, Kuwait, Morocco, Philippines, Romania, Spain, and Turkey. The other 24 Member States of the Board are also given

The International Atomic Energy Agency - IAEA

International Nuclear Information System (INIS)

Pezzutti, A.A.C.

1980-01-01

The origens, functions and objectives of the IAEA are analysed. The application of safeguards to avoid military uses of nuclear energy is discussed. In the final section the agrement between Brazil and Germany regarding IAEA safeguards, as well as the competence for executing the brazilian program are explained. It is, then, an informative study dealing with nuclear energy and its peaceful path, the creation of International Fuel Cycle Evaluation and nonproliferation [pt

Guidelines for the review research reactor safety. Reference document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

International Nuclear Information System (INIS)

1997-01-01

In 1992, the IAEA published new safety standards for research reactors as part of the set of publications considered by its Research Reactor Safety Programme (RRSP). This set also includes publications giving guidance for all safety aspects related to the lifetime of a research reactor. In addition, the IAEA has also revised the Safety Standards for radiation protection. Consequently, it was considered advisable to revise the Integrated Safety Assessment of Research Reactors (INSARR) procedures to incorporate the new requirements and guidance as well as to extend the scope of the safety reviews to currently operating research reactors. The present report is the result of this revision. The purpose of this report is to give guidance on the preparation, execution, reporting and follow-up of safety review mission to research reactors as conducted by the IAEA under its INSARR missions safety service. However, it will also be of assistance to operators and regulators in conducting: (a) ad hoc safety assessments of research reactors to address individual issues such as ageing or safety culture; and (b) other types of safety reviews such as internal and peer reviews and regulatory inspections

A brief history of NDA at the IAEA

International Nuclear Information System (INIS)

Sprinkle, J.K.; Sinkule, B.J.; Hsue, S.-T.; Abhold, M.E.

2001-01-01

Nearly 30 years ago, the first portable nondestructive assay instrument, a SAM-II, was brought to Vienna for IAEA consideration. This initial foray into the usage of nondestructive assay (NDA) as an independent assessment tool has materialized into one of the important tools for IAEA inspections. NDA instruments have several inherent advantages for inspectors; their measurements generate no radioactive waste, provide immediate answers, do not require specialized operators, and can be either taken to the items to be measured (portable instruments), or the items for measurement can be brought to the instruments, such as can be applied in on-site IAEA laboratories or off-site IAEA lab at Siebersdorf. The SAM-II was a small, lightweight, battery-powered, gamma-ray instrument used for uranium enrichment measurements. It was also found to be usehl for locating nuclear material, distinguishing between uranium and plutonium, and determining the active length of items like fuel pins. However it was not well suited for determining the amount of bulk material present, except for small containers of low-density materials. A 6-sided neutron coincidence counter, easily disassembled so it could be shipped and carried by airplane, was developed for bulk measurements of plutonium. The HLNCC (High Level Neutron Coincidence Counter) was immediately useful for quantitative measurements of pure plutonium oxide. However, the IAEA had to make a trade-off between the ease of use of NDA instruments on-site, and the problems of obtaining small samples for shipment to an independent lab for more accurate analysis. NDA does not create radioactive waste, so as waste handling has become more cautious and more regulated, NDA looks better and better. After acceptance of NDA by the IAEA for routine use, the follow-up question was naturally, 'How much better can this measurement be made?' The Program for Technical Assistance to IAEA Safeguards (POTAS) supported multiple and varied efforts in this

IAEA Expert Team Concludes Mission to Onagawa NPP

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA team of international experts today delivered its initial report at the end of a two-week mission to gather information about the effects of the Great East Japan Earthquake on the Onagawa Nuclear Power Station (NPS), saying the plant was 'remarkably undamaged'. Findings from the visual investigation will be added to an IAEA data base being compiled by its International Seismic Safety Centre (ISSC) to provide knowledge for Member States about the impact of external hazards on nuclear power plants. The ISSC data bank makes an important contribution to the IAEA's Action Plan on Nuclear Safety, which was unanimously endorsed by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi NPS. Onagawa, facing the Pacific Ocean on Japan's north-east coast, was the nuclear power plant closest to the epicentre of the 11 March 2011 magnitude 9.0 earthquake that struck Japan and resulted in a devastating tsunami. The plant experienced very high levels of ground shaking - among the strongest of any plant affected by the earthquake - and some flooding from the tsunami that followed, but was able to shut down safely. In its draft report the team said that 'the structural elements of the NPS were remarkably undamaged given the magnitude of ground motion experienced and the duration and size of this great earthquake'. The mission's objective was to observe how structures, systems and components with significance to the safety of the plant responded to the earthquake and heavy shaking. At the damaged Fukushima Daiichi NPS, nearly 120 km south of Onagawa NPS, the effects of the earthquake, tsunami and hydrogen explosions make it impossible to single out the impact of external hazards on safety-related parts of the power station. The Government of Japan and the IAEA therefore agreed to deploy a mission to the three-unit Onagawa NPS. The team's 19 members from six countries, including IAEA staff, held discussions with the operators of the

Operating trends and performance of nuclear power plants in IAEA member states

International Nuclear Information System (INIS)

Galori, F.

1984-01-01

The present status and short-term development of nuclear power programmes in IAEA member states is reviewed. A description of the IAEA Power Reactor Information System (PRIS) is given and the objectives for data collection and treatment are discussed. As indicated by the reports at the IAEA International Conference on Nuclear Power experience in 1982, there are considerable differences in the performances of nuclear power plants even within classes of plants which technically should be very similar and thus perform equally well. PRIS permist at least some preliminary conclusions about the reasons for differences to be drawn. It is becoming clear that reasons for good or bad performance must be sought in a number of factors including: type of plant (on-load/off-load refuelling, GCR, PHWR, LWR); age and vintage of plant; manufacturer of the main plant system; degree of standardization in plant and construction; competence of operating organization; regulatory climate. Analysis of the reported outages shows that major problems are: stress corrosion cracking in primary piping, also denting and wall thinning in tubes of steam generators; thermal fatigue cracking in the feedwater system and excessive errosion/corrosion problems in turbines. It is emphasized that international cooperation is important for creating an effective system for learning from operating experience

Guidelines for preparing IAEA design information questionnaires

International Nuclear Information System (INIS)

Swartz, J.M.; Bieber, A.M.

1980-01-01

The format of the IAEA Design Information Questionnaires and the SAI prepared guidelines for completing them, is described. The guidelines should assist facility operators in meeting the time constraints set forth in the Subsidiary Arrangements by effectively supplying the information needed by the IAEA and in minimizing resource allocations to the preparation effort. 8 refs

IRS Guidelines: Joint IAEA/NEA International Reporting System for Operating Experience

International Nuclear Information System (INIS)

2010-01-01

The International Reporting System for Operating Experience (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the OECD Nuclear Energy Agency (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants which are operated worldwide. This objective can be achieved by providing timely and detailed information on lessons learned from operating and construction experience at the international level. This information could be related to issues and events that are related to safety. The purpose of these guidelines is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the effectiveness of the system expected by all Member States operating nuclear power plants. As this system is owned by the Member States, the IRS Guidelines have been developed and approved by the IRS National Co-ordinators with the assistance of both Secretariats (IAEA/NEA).

Neutron activation analysis of Standard Materials of Comparison IAEA- the corn and soya flour

International Nuclear Information System (INIS)

Dadakhanov, J.A.; Sadykov, I.I.; Salimov, M.I.

2005-01-01

It is known that maintenance of quality of results of neutron activation analysis (NAA), no less than in other analytical methods, is one of key problems. Thus first of all it is necessary to provide correctness of results. The most correct way of revealing and elimination of regular errors is carrying out of analyses of Standard Samples of Comparison (SSC) by the developed techniques and comparison of the received results with the certificated results. Therefore, the analysis and certification of various SSC is one of the most actual tasks of modern analytical chemistry. One of few organizations engaged in manufacture SSC for NAA, is IAEA which has organized the Project on certification of samples of comparison - a corn and soya flour. Among many laboratories worldwide, in this Project the Laboratory of the Activation Analysis of Pure Materials of Institute of Nuclear Physics Academy of Sciences Republic of Uzbekistan also participated. We carry out series of analyses of samples of corn and soya flour, candidates for standard samples of comparison, by the method of instrumental NAA. The preparing of samples was carried out by the technique described in the technical project applied to these materials. Samples before the analysis dried up at temperature 80 degree C during 24 h. Cooled, weighed and irradiated in the vertical channel of a nuclear reactor of VVR-SM of Institute of Nuclear Physics Academy of Sciences Republic of Uzbekistan during 0,5-1 h (depending on determined elements) with density of a stream of neutrons 1 x 10 14 neutrons/cm 2 sec. Time of cooling from 10 min up to 10 days. Time of measurement from 100 sec up to 3000 sec. Measurements were carried out on gamma spectrometer consisting of HPGe detector GC1518 and digital multichannel analyzer DSA-1000('Canberra', USA). Processing of the spectrometer information carried out with the help of software package Genie-2000. As a result of the carried out analyses we determine contents of 21 elements in

IAEA Director General to visit Libya

International Nuclear Information System (INIS)

2003-01-01

Full text: Dr. Mohamed ElBaradei announced today that he will visit the Libyan Arab Jamahiriya (Libya) in the immediate future with a team of senior IAEA technical experts. 'The purpose of my visit will be to initiate an in-depth process of verification of all of Libya's past and present nuclear activities', Dr. ElBaradei said in a news conference. 'We shall define the corrective actions that need to be taken and consult on the necessary steps to eliminate any weapons related activities.' The announcement follows a meeting held in Vienna on 20 December 2003 between Dr. ElBaradei and H.E. Engineer Matooq Mohamed Matooq, Assistant Secretary for Services Affairs of the General People's Committee of Libya. In that meeting, Mr. Matooq informed Dr. ElBaradei of Libya's decision to eliminate 'materials, equipments and programmes which lead to the production of internationally proscribed weapons'. The Agency was also informed that Libya had been engaged for more than a decade in the development of a uranium enrichment capability. This included importing natural uranium and centrifuge and conversion equipment and the construction of now dismantled pilot scale centrifuge facilities. Some of these activities should have been, but were not, reported to the IAEA under Libya's Safeguards Agreement with the IAEA. Mr. Matooq stated, however, that Libya's nuclear enrichment programme was at an early stage of development and that no industrial scale facility had been built, nor any enriched uranium produced. Libya has asked the IAEA to ensure through verification that all of Libya's nuclear activities will henceforth be under safeguards and exclusively for peaceful purposes. In that regard, Libya has agreed to take the necessary steps to conclude an Additional Protocol to its NPT Safeguards Agreement, which will provide the IAEA with broader inspection rights, and to pursue with the IAEA a policy of full transparency and active co-operation. Dr. ElBaradei said, 'Libya's decision to

Development through science: The IAEA research contract programme

International Nuclear Information System (INIS)

Benson Wiltschegg, T.; Gillen, V.

1991-01-01

The IAEA strives to stimulate the growth of science in developing countries by assuring that the IAEA and the scientific communities of developed and developing countries share their knowledge and experience. If the assistance provided is well organized and in keeping with the needs of developing countries it can make the crucial difference in sustainable development. This booklet provides a survey of the historical development of the IAEA's Research Contract Programme and outlines the aims and achievements of selected Co-ordinated Research Programmes. A complete listing of Co-ordinated Research Programmes is provided

The IAEA and non-proliferation: is quiescence progress

International Nuclear Information System (INIS)

Herron, L.W.

1983-01-01

The purpose of this paper is to evaluate the current status of more important non-proliferation aspects affecting or involving the IAEA. The questions dealt with cover in particular the Non-Proliferation Treaty, the Tlatelolco Treaty, the Committee on Assurances of Supply established by the IAEA in 1980 and the International Plutonium Storage Study prepared by an IAEA expert group. The author concludes that in a number of areas involving this Agency, recent considerable activity at both political and technical levels has produced few tangible results althrough the situation is not static. (NEA) [fr

Independent Auditor's Approach to the Concept of Fraud in Accounting Standards

Directory of Open Access Journals (Sweden)

Handan Bulca

2015-07-01

Full Text Available Control in the field of standards, quality and safety can be increased fraud and error reduction is envisaged. In parallel with these changes, the conditions in the Official Gazette dated 14 March 2014 to companies that provide audit is mandatory. With the implementation of auditing standards and corporate companies will become more transparent. Information users more secure thanks to the information reaching these standards will be able to make healthy decisions. The study also has redefined the concept of independent auditors and the audit process should follow an independent auditor, is also indicated. The focus of the study of the risk of fraud and cheating, Independent Auditing Standards Number 240 constitutes in terms of views.

Training the IAEA Inspectors

International Nuclear Information System (INIS)

Potterton, L.

2010-01-01

Newly recruited safeguards inspectors take to the field. There are currently 250 inspectors and every year the IAEA runs an introductory course on the safeguards systems for the organisation's newly appointed inspectors.

Water chemistry-related activities at the IAEA

International Nuclear Information System (INIS)

Cheng, H.; Onufriev, V.

2005-01-01

Water chemistry activities and publications in the past are listed. IAEA Coordinated Research Programmes, WWER-1000 SG water chemistry database, materials issues TM in Vienna, TC workshops and attendance of international meetings, publications. There is a list of IAEA publications related to water chemistry and corrosion. Finally water chemistry activities planned for 2006-2008 are detailed. (N.T.)

IAEA Newsbriefs. V. 12, no.1(74). Jan-Feb 1997

International Nuclear Information System (INIS)

1997-01-01

This issue gives brief information on the following topics: IAEA Board of Governors meeting in March, 40th anniversary activities include publication of book on IAEA's history, First preparatory meeting of Parties to Nuclear Safety Convention, African countries seek end of 'cattle plague', Isotope in marine environmental studies, Safe management of spent fuel from research reactors, Upcoming IAEA seminars and symposia, Exemption, exclusion, and clearance of radiation sources, Recent IAEA publications, Cuba to host international symposium, Tlatelolco Treaty marks 30th anniversary signing, and other short information

Statement to the 46th regular session of the IAEA General Conference 2002. Vienna, 16 September 2002

Energy Technology Data Exchange (ETDEWEB)

ElBaradei, M [International Atomic Energy Agency, Vienna (Austria)

2002-09-16

In his Statement to the forty-six regular session of the General Conference of the IAEA, the Director General of the Agency highlighted some of the IAEA's activities and challenges in the fields of: nuclear operation and construction; radioactive waste management; nuclear applications; radiotherapy; sterile insect technique; water resources management; international co-operation and conventions; establishment of global safety standards; radiation protection; management of nuclear knowledge; safeguards; implementation of United Nations Security Council resolutions relating to Iraq; convention on the physical protection of nuclear material. He also discussed the Agency's technical co-operation programme and the Agency management.

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide provides recommendations on achieving and demonstrating compliance with IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, establishing safety requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material; these include the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Series No. TS-G-1.1, 2002 Edition

Statement to the 46th regular session of the IAEA General Conference 2002. Vienna, 16 September 2002

International Nuclear Information System (INIS)

ElBaradei, M.

2002-01-01

In his Statement to the forty-six regular session of the General Conference of the IAEA, the Director General of the Agency highlighted some of the IAEA's activities and challenges in the fields of: nuclear operation and construction; radioactive waste management; nuclear applications; radiotherapy; sterile insect technique; water resources management; international co-operation and conventions; establishment of global safety standards; radiation protection; management of nuclear knowledge; safeguards; implementation of United Nations Security Council resolutions relating to Iraq; convention on the physical protection of nuclear material. He also discussed the Agency's technical co-operation programme and the Agency management

IAEA Post Irradiation Examination Facilities Database

International Nuclear Information System (INIS)

Jenssen, Haakon; Blanc, J.Y.; Dobuisson, P.; Manzel, R.; Egorov, A.A.; Golovanov, V.; Souslov, D.

2005-01-01

The number of hot cells in the world in which post irradiation examination (PIE) can be performed has diminished during the last few decades. This creates problems for countries that have nuclear power plants and require PIE for surveillance, safety and fuel development. With this in mind, the IAEA initiated the issue of a catalogue within the framework of a coordinated research program (CRP), started in 1992 and completed in 1995, under the title of ''Examination and Documentation Methodology for Water Reactor Fuel (ED-WARF-II)''. Within this program, a group of technical consultants prepared a questionnaire to be completed by relevant laboratories. From these questionnaires a catalogue was assembled. The catalogue lists the laboratories and PIE possibilities worldwide in order to make it more convenient to arrange and perform contractual PIE within hot cells on water reactor fuels and core components, e.g. structural and absorber materials. This catalogue was published as working material in the Agency in 1996. During 2002 and 2003, the catalogue was converted to a database and updated through questionnaires to the laboratories in the Member States of the Agency. This activity was recommended by the IAEA Technical Working Group on Water Reactor Fuel Performance and Technology (TWGFPT) at its plenary meeting in April 2001. The database consists of five main areas about PIE facilities: acceptance criteria for irradiated components; cell characteristics; PIE techniques; refabrication/instrumentation capabilities; and storage and conditioning capabilities. The content of the database represents the status of the listed laboratories as of 2003. With the database utilizing a uniform format for all laboratories and details of technique, it is hoped that the IAEA Member States will be able to use this catalogue to select laboratories most relevant to their particular needs. The database can also be used to compare the PIE capabilities worldwide with current and future

International nuclear safety experts conclude IAEA peer review of China's regulatory system

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of senior experts on nuclear safety regulation today completed a two-week International Atomic Energy Agency (IAEA) review of the governmental and regulatory framework for nuclear safety in the People's Republic of China. The team identified good practices within the system and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of the People's Republic of China. The final report will be submitted to China by Autumn 2010. At the request of Chinese authorities, the IAEA assembled a team of 22 experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This mission is a peer review based on the IAEA Safety Standards . It is not an inspection, nor an audit. The experts came from 15 different countries: Australia, Canada, the Czech Republic, Finland, France, Hungary, Japan, Pakistan, the Republic of Korea, Slovenia, South Africa, Sweden, the United Kingdom, Ukraine and the United States. Mike Weightman, the United Kingdom's Head of Nuclear Directorate, HSE and HM Chief Inspector of Nuclear Installations said: ''I was honoured and pleased to lead such a team of senior regulatory experts from around the world, and I was impressed by their commitment, experience and hard work to provide their best advice possible. We had very constructive interactions with the Chinese authority to maximize the beneficial impact of the mission.'' The scope of the mission included the regulation of nuclear and radiation safety of the facilities and activities regulated by the Ministry of Environmental Protection (MEP) National Nuclear Safety Administration (NNSA). The mission was conducted from 18 to 30 July, mainly in Beijing. To observe Chinese regulatory activities, the IRRS team visited several nuclear facilities, including a nuclear power plant, a manufacturer of safety components for nuclear power plants, a research reactor, a fuel cycle facility, a waste management facility